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STP156320120040: Tribocorrosion in Pressurized Water Reactors - 01 May 2013

STP156320120035: Development of a Predictive Wear Model for Grid-to-Rod Fretting in Light Water Nuclear Reactors - 01 May 2013

STP156320120118: An Approach to Mapping the Erosion–Corrosion of Stainless Steel: Applications to Tidal Energy Systems - 01 May 2013

STP103947: Approach of He/dpa Synergistic Effects in Iron-Based Materials Using JANNUS - 01 January 2013

STP1547-EB: Effects of Radiation on Nuclear Materials: 25th Volume - 01 January 2013

STP103948: Use of MeV Ion Beams to Simulate the Irradiation Effects in Advanced Materials at JANNUS Saclay - 01 January 2013

STP104242: Embrittlement of Nickel Alloys in a CANDU Reactor EnvironmentCANDU (CANadian Deuterium Uranium)® is a registered trademark or Atomic Energy of Canada Limited. - 01 January 2013

STP104128: Material Investigations on Highly Irradiated Aluminum Magnesium Alloys for Lifetime Assessment of a Neutron Beam Tube in the BER II Research Reactor - 01 January 2013

STP103999: A Wide-Range Embrittlement Trend Curve for Western Reactor Pressure Vessel Steels - 01 January 2013

STP103980: (U)HMWPE as Neutron Radiation Shielding Materials: Impact of Gamma Radiation on Structure and Properties - 01 January 2013

STP104113: Long Term Irradiation Phenomena in RPV Steels—The LONGLIFE Project - 01 January 2013

STP20120069: Microstructure Response of WWER-440 Reactor Pressure Vessel Weld Material After Irradiation and Annealing Treatment - 01 January 2013

STP104128T: Material Investigations on Highly Irradiated Aluminum Magnesium Alloys for Lifetime Assessment of a Neutron Beam Tube in the BER II Research Reactor - 01 November 2012

STP1547-EB: Effects of Radiation on Nuclear Materials: 25th Volume - 01 November 2012

STP104601: Evaluation of Repaired Gas Turbine Engine Bearings Demonstrates Absence of Subsurface Fatigue Propagation in Appropriately Designed Applications - 01 October 2012

STP1550-EB: Reactor Dosimetry: 14th International Symposium - 01 August 2012

STP1529-EB: Zirconium in the Nuclear Industry: 16th International Symposium - 01 April 2012

JAI103605: Characteristics of PAG Based Bio-Hydraulic Fluid - 01 January 2012

JAI103627: A New Way to Determine the Biodegradability of Lubricants by a Biokinetic Model - 01 January 2012

STP1529-EB: Zirconium in the Nuclear Industry: 16th International Symposium - 01 December 2011

STP1477-EB: Biofuels - 01 January 2011

STP49345S: Monitoring and Blending Biofuels Using a Microfluidic Sensor - 01 January 2011

STP49346S: Compositional Analysis of Microwave Chemically Treated Biomass Samples - 01 January 2011

STP49347S: Calibration Standards for Biodiesel Fuels - 01 January 2011

STP49348S: A Simple Green Method for Biodiesel Iodine Number Determination - 01 January 2011

STP49349S: Potentiometric Titration as an Alternative Technique for the Determination of the Iodine Value in Biodiesel Matrix from Palm Oil - 01 January 2011

STP49350S: Acid Number Determination of Biodiesel by Potentiometric Titration Using Different Methods - 01 January 2011

STP49351S: Determination of Ester Content in Different Kinds of Biodiesel - 01 January 2011

STP49353S: Determining the Oxidation Stability of Biodiesel and Blends Using a New Rapid Small Scale Oxidation Test (RSSOT)—The PetroOXY - 01 January 2011

STP49354S: The Impact of Fischer—Tropsch Diesel on the Oxidation Stability of Biodiesel (FAME) Blends - 01 January 2011

STP49356S: pH Measurement in Bioethanol by Using Different Electrodes and according to International Standards - 01 January 2011

STP49357S: Cold Flow Properties of Biodiesel by Automatic and Manual Analysis Methods - 01 January 2011

STP49358S: The Influence of the Addition of Oils in the Diesel Fuel Density - 01 January 2011

STP49359S: Synthesis of Biodiesel from Tobacco and Waste Frying Oil Using Heterogeneous KHCO3/Al2O3 Catalyst - 01 January 2011

STP49341S: Oxidation Stability of Soy and Palm Based Biodiesels Evaluated by Pressure Differential Scanning Calorimetry - 01 January 2011

STP49360S: Performance Characteristics of a Dual Fuel Engine Operated with Mahua Biodiesel and Liquefied Petroleum Gas - 01 January 2011

STP49361S: Biodiesel Synthesis via Recyclable Heterogeneous Catalyst: Titanium Niobate Nanosheet - 01 January 2011

STP49362S: Experimental Investigations of Preheated Jatropha Oil Fuelled Direct Injection Compression Ignition Engine—Part 1: Performance, Emission, and Combustion Characteristics - 01 January 2011

STP49363S: Experimental Investigation of Preheated Jatropha Oil Fuelled Direct Injection Compression Ignition Engine—Part 2: Engine Durability and Effect on Lubricating Oil - 01 January 2011

STP49364S: Characterization of Density of Biodiesel from Soybean, Sunflower, Canola, and Beef Tallow in Relation to Temperature, Using a Digital Density Meter with a Metrological Point of View - 01 January 2011

STP49365S: Lipase-Catalyzed Production of Biodiesel from Tallow - 01 January 2011

STP49340S: Analytical Characterization of Sediment Formed in Soy Oil-Based B20 Biodiesel - 01 January 2011

STP49367S: The Potential of Biodiesel Production from Fatty Acid Methyl Esters of Some European/Mediterranean and Cosmopolitan Halophyte Seed Oils - 01 January 2011

STP49342S: Water Content Determination in Biodiesel: Optimization of Methodology in Coulometric Karl Fischer Titration - 01 January 2011

STP49370S: ASTM Proficiency Testing Programs for Biofuels - 01 January 2011

STP49372S: Pretreatment of Douglas Fir Wood Biomass for Improving Saccharification Efficiencies - 01 January 2011

STP49343S: Standard Reference Data for the Thermophysical Properties of Biofuels - 01 January 2011

STP49344S: Challenge of Analytical Characterization of Biofuels - 01 January 2011

STP49276S: Author Index - 01 January 2011

STP49277S: Subject Index - 01 January 2011

STP49281S: Investigation of Transition Fracture Toughness Variation within the Thickness of Reactor Pressure Vessel Forgings - 01 January 2011

STP49279S: - 01 January 2011

STP49929S: Lubricating Oils Evaluation of Dispersancy Capacity of Lubricating Oils and the Impact of Biofuels on Lubricant Dispersancy - 01 January 2011

STP49930S: Experiences with ASTM D02 Practices D4378 and D6224 for Turbine Oils and Auxiliary Power Plant Equipment Condition Monitoring Programs - 01 January 2011

STP49922S: Optimizing a Wind Turbine Oil Condition Monitoring Program - 01 January 2011

JAI102127: Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Materials - 01 May 2010

STP1513-EB: Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle: 24th Volume - 01 May 2010

STP49005S: Investigation of Beltline Welding Seam of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel - 01 January 2010

STP1513-EB: Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle: 24th Volume - 01 January 2010

STP49006S: Microstructural Characterization of RPV Materials Irradiated to High Fluences at High Flux - 01 January 2010

STP49007S: Irradiation-Induced Grain-Boundary Solute Segregation and Its Effect on Ductile-to-Brittle Transition Temperature in Reactor Pressure Vessel Steels - 01 January 2010

STP49008S: Irradiation-Induced Hardening and Embrittlement of High-Cr ODS Ferritic Steels - 01 January 2010

STP49009S: Kinetic Monte Carlo Simulation of Helium-Bubble Evolution in ODS Steels - 01 January 2010

STP49010S: Study of Microstructure and Property Changes in Irradiated SS316 Wrapper of Fast Breeder Test Reactor - 01 January 2010

STP49000S: International Atomic Energy Agency Coordinated Research Projects on Structural Integrity of Reactor Pressure Vessels - 01 January 2010

STP49011S: Unusual Enhancement of Ductility Observed during Evolution of a “Deformation Wave” in 12Cr18Ni10Ti Stainless Steel Irradiated in BN-350 - 01 January 2010

STP49012S: Interrelationship between True Stress—True Strain Behavior and Deformation Microstructure in the Plastic Deformation of Neutron-Irradiated or Work-Hardened Austenitic Stainless Steel - 01 January 2010

STP49013S: Influence of Neutron Irradiation on Energy Accumulation and Dissipation during Plastic Flow and Hardening of Metallic Polycrystals - 01 January 2010

STP49014S: Comparison of CANDU Fuel Bundle Finite Element Model with Unirradiated Mechanical Load Experiments - 01 January 2010

STP49001S: Analysis of the Belgian Surveillance Fracture Toughness Database Using Conventional and Advanced Master Curve Approaches - 01 January 2010

STP49002S: Final Results from the Crack Initiation and Arrest of Irradiated Steel Materials Project on Fracture Mechanical Assessments of Pre-Irradiated RPV Steels Used in German PWR - 01 January 2010

STP49004S: Magnox Steel Reactor Pressure Vessel Monitoring Schemes—An Overview - 01 January 2010

STP49152S: A Novel Approach to Model Moving Heat Sources - 01 January 2010

STP48727S: Fracture Toughness Evaluation of Eurofer97 by Testing Small Specimens - 01 January 2009

STP1502-EB: Small Specimen Test Techniques: 5th Volume - 01 January 2009

STP48728S: Effect of Ta Rich Inclusions and Microstructure Change during Precracking on Bimodal Fracture of Reduced-Activation Ferritic∕Martensitic Steels Observed in Transition Range - 01 January 2009

STP48729S: Application of Subsize Specimens for Irradiation Embrittlement Monitoring of VVER-440∕213 RPV Steels - 01 January 2009

STP48730S: Effects of Surface Morphology and Distributed Inclusions on the Low Cycle Fatigue Behavior of Miniaturized Specimens of F82H Steel - 01 January 2009

STP48731S: Use of KLST-Type Miniature Charpy Specimens for Measuring Dynamic Fracture Toughness under Impact Loading Rates - 01 January 2009

STP48732S: Determination of Transferable Lower-Bound Fracture Toughness from Small Specimens - 01 January 2009

STP48721S: Miniature Compact Tension Specimens for Upper Shelf Fracture Toughness Measurements on RPV Steels - 01 January 2009

STP48733S: Surveillance of the Fracture Behavior of Zircaloy-4 Welds Using the Small Punch Test - 01 January 2009

STP48720S: Specimen Size Limitations in J-R Curve Testing—Standards versus Reality - 01 January 2009

STP48734S: Application of the Small-Punch Test to Irradiated Reactor Vessel Steels in the Brittle-Ductile Transition Region - 01 January 2009

STP48735S: Investigation of Material Fatigue Behavior through Cyclic Ball Indentation Testing - 01 January 2009

STP48722S: Using Subsize Impact Bend Specimens for Estimation of Irradiation and Re-Irradiation Embrittlement of VVER RPV Steels - 01 January 2009

STP48723S: Towards Crack Arrest Testing Using Miniature Specimens - 01 January 2009

STP48724S: Application of Subsize Specimens for Re-Irradiation Embrittlement Monitoring of the First Generation of VVER-440 RPV Steels - 01 January 2009

STP48725S: Application of Digital Marker Extensometry to Determine the True Stress-Strain Behavior of Irradiated Metals and Alloys - 01 January 2009

STP48726S: Crack Arrest Testing Using Small Wide Plate SE(T) Specimens - 01 January 2009

STP48133S: Experimental and Analytical Investigation of the Mechanical Behavior of High-Burnup Zircaloy-4 Fuel Cladding - 01 January 2009

STP1505-EB: Zirconium in the Nuclear Industry: 15th International Symposium - 01 January 2009

STP48134S: Effect of Local Hydride Accumulations on Zircaloy Cladding Mechanical Properties - 01 January 2009

STP48135S: Fracture Toughness of Hydrided Zircaloy-4 Sheet under through-Thickness Crack Growth Conditions - 01 January 2009

STP48136S: Characterization of Local Strain Distribution in Zircaloy-4 and M5® Alloys - 01 January 2009

STP48137S: In-Pile Criteria for the Initiation of Massive Hydriding of Zr in Steam-Hydrogen Environment - 01 January 2009

STP48138S: Round-Robin Testing of Fracture Toughness Characteristics of Thin-Walled Tubing - 01 January 2009

STP48139S: Role of Twinning and Slip in Deformation of a Zr-2.5Nb Tube - 01 January 2009

STP48140S: Measurement of Rates of Delayed Hydride Cracking (DHC) in Zr-2.5Nb Alloys—An IAEA Coordinated Research Project - 01 January 2009

STP48141S: A Study of the Structure and Chemistry in Zircaloy-2 and the Resulting Oxide After High Temperature Corrosion - 01 January 2009

STP48142S: Effects of Pt Surface Coverage on Oxidation of Zr and Other Materials - 01 January 2009

STP48129S: Characterization of Zirconium Hydrides and Phase Field Approach to a Mesoscopic-Scale Modeling of Their Precipitation - 01 January 2009

STP48143S: Studies of Corrosion of Cladding Materials in Simulated BWR Environment using Impedance Measurements - 01 January 2009

STP48144S: In Situ EIS Measurements of Irradiated Zircaloy-4 Post-Transition Corrosion Kinetic Behavior - 01 January 2009

STP48145S: Effect of Water Chemistry and Composition on Microstructural Evolution of Oxide on Zr Alloys - 01 January 2009

STP48146S: The Effect of Hydrogen on the Transition Behavior of the Corrosion Rate of Zirconium Alloys - 01 January 2009

STP48147S: A New Model to Predict the Oxidation Kinetics of Zirconium Alloys in a Pressurized Water Reactor - 01 January 2009

STP48148S: In PWR Comprehensive Study of High Burn-Up Corrosion and Growth Behavior of M5® and Recrystallized Low-Tin Zircaloy-4 - 01 January 2009

STP48149S: ZIRLO™ Cladding Improvement - 01 January 2009

STP48150S: Corrosion and Oxide Properties of HANA Alloys - 01 January 2009

STP48151S: Microstructural Characterization of Oxides Formed on Model Zr Alloys Using Synchrotron Radiation - 01 January 2009

STP48152S: Chemistry of Waterside Oxide Layers on Pressure Tubes - 01 January 2009

STP48153S: Manufacturing Variability, Microstructure, and Deformation of Zr-2.5Nb Pressure Tubes - 01 January 2009

STP48130S: Influence of Structure Changes in E110 Alloy Claddings on Ductility Loss under LOCA Conditions - 01 January 2009

STP48154S: Effect of Irradiation Damage on the Deformation Properties of Zr-2.5Nb Pressure Tubes - 01 January 2009

STP48155S: Determination and Interpretation of Texture Evolution during Deformation of a Zirconium Alloy - 01 January 2009

STP48156S: Irradiation-Induced Growth and Microstructure of Recrystallized, Cold Worked and Quenched Zircaloy-2, NSF, and E635 Alloys - 01 January 2009

STP48157S: Deformation Anisotropy of Annealed Zircaloy-2 as a Function of Fast Neutron Fluence - 01 January 2009

STP48158S: Toward a Better Understanding of Dimensional Changes in Zircaloy-4: What is the Impact Induced by Hydrides and Oxide Layer? - 01 January 2009

STP48159S: CASTA DIVA®: Experiments and Modeling of Oxide-Induced Deformation in Nuclear Components - 01 January 2009

STP48160S: Cladding Tube Deformation Test for Stress Reorientation of Hydrides - 01 January 2009

STP48161S: Evaluation of Hydride Reorientation Behavior and Mechanical Properties for High-Burnup Fuel-Cladding Tubes in Interim Dry Storage - 01 January 2009

STP48162S: Experimental and Modeling Approach of Irradiation Defects Recovery in Zirconium Alloys: Impact of an Applied Stress - 01 January 2009

STP48163S: Mechanical Properties of Zr-2.5Nb Pressure Tubes Made from Electrolytic Powder - 01 January 2009

STP48131S: Investigations of the Microstructure and Mechanical Properties of Prior-β Structure as a Function of the Oxygen Content in Two Zirconium Alloys - 01 January 2009

STP48164S: Structure-Phase State, Corrosion and Irradiation Properties of Zr-Nb-Fe-Sn System Alloys - 01 January 2009

STP48165S: Investigation of Structural and Chemical Uniformity of Zr2.5% Nb and E635 Alloy by Radioactive Indicators - 01 January 2009

STP48166S: Contribution of Thermodynamic Calculations to Metallurgical Studies of Multi-Component Zirconium Based Alloys - 01 January 2009

STP48167S: Intergranular and Interphase Constraints in Zirconium Alloys - 01 January 2009

STP48168S: Tearing Crack Growth and Fracture Micro-Mechanisms Under Micro Segregation in Zr-2.5%Nb Pressure Tube Material - 01 January 2009

STP48132S: Hydrogen Content, Preoxidation, and Cooling Scenario Effects on Post-Quench Microstructure and Mechanical Properties of Zircaloy-4 and M5® Alloys in LOCA Conditions - 01 January 2009

STP48708S: Soil Water Measurements Relevant to Agronomic and Environmental Functions of Chemically Treated Soil - 01 January 2009

STP48784S: Introducing Heterogeneity into Brittle Fracture Modeling of a 22NiMoCr37 Ferritic Steel Ring Forging - 01 January 2009

STP48785S: Stress-Triaxiality in Zr-2.5Nb Pressure Tube Materials - 01 January 2009

STP48791S: Carrying Capacity Prediction of Steam Turbine Rotors with Operation Damage - 01 January 2009

STP48840S: Sealed Aluminum Cavity Reactions When Submerged in Pure O2 Reboiler Sump - 01 January 2009

STP45729S: Varnish Formation in the Gas Turbine Oil Systems - 01 January 2008

STP1489-EB: Oxidation and the Testing of Turbine Oils - 01 January 2008

STP45720S: Oxidation Fundamentals and Its Application to Turbine Oil Testing - 01 January 2008

STP45721S: Modern Turbine Oil Oxidation Performance Limits—Meeting and Measuring Them—A Shell Perspective - 01 January 2008

STP45722S: Physical, Performance, and Chemical Changes in Turbine Oils from Oxidation - 01 January 2008

STP45723S: Studies of the Oxidation Dynamics of Turbine Oils—Initial Data from a New Form of the Rotating Pressure Vessel Oxidation Test - 01 January 2008

STP45724S: Review of Degradation Mechanisms Leading to Sludge and Varnish in Modern Turbine Oil Formulations - 01 January 2008

STP45725S: Contamination of Power Generation Lubricants - 01 January 2008

STP45726S: Evaluation and Comparison Between Oxidation Stability Test Methods for Turbine Oils - 01 January 2008

STP45727S: Residue Analysis on RPVOT Test Samples for Single and Multiple Antioxidants Chemistry for Turbine Lubricants - 01 January 2008

STP45728S: Oxidation Testing of Long-Life Turbine Oil Fluids. Can We Do Better? - 01 January 2008

STP46568S: Strain Hardening During Mechanical Twinning and Dislocation Channeling in Irradiated 316 Stainless Steels - 01 January 2008

STP1492-EB: Effects of Radiation on Materials: 23rd International Symposium - 01 January 2008

STP46569S: Notch Strengthening and Its Impact on the Deformation and Fracture of 316L Stainless Steel - 01 January 2008

STP46570S: Irradiation Hardening and Microstructure Evolution of Ion-irradiated ODS Ferritic Steels - 01 January 2008

STP46571S: Modelling of Radiation Damage in Fe-Cr Alloys - 01 January 2008

STP46561S: The Feasibility of Using a Risk-informed Approach for Calculating Reactor Pressure Vessel Heatup and Cooldown Operating Curves - 01 January 2008

STP46572S: Kinetics of the Migration and Clustering of Extrinsic Gas in bcc Metals - 01 January 2008

STP46573S: Modeling the Interaction of Helium with Dislocations and Grain Boundaries in Alpha-Iron - 01 January 2008

STP46574S: DD Simulations of Dislocation-Crack Interaction During Fatigue - 01 January 2008

STP46575S: Grain Growth in Nanocrystalline Metal Thin Films under In Situ Ion-Beam Irradiation - 01 January 2008

STP46576S: Microstructural Features in Aged Erbium Tritide Films - 01 January 2008

STP46577S: Internal Probe to Detect Defects from Cascades—In-situ Ion Irradiation Experiments Revisited - 01 January 2008

STP46562S: Monitoring of Radiation Embrittlement of the First and Second Generation of VVER RPV Steels - 01 January 2008

STP46560S: Master Integrated Reactor Vessel Surveillance Program - 01 January 2008

STP46563S: Analysis of the Ductile-to-Brittle Transition Temperature Shift in a Commercial Power Plant With High Nickel Containing Weld Material - 01 January 2008

STP46564S: Radiation Embrittlement of Cr-Ni-Mo and Cr-Mo RPV Steels - 01 January 2008

STP46565S: Attenuation of Neutron Radiation Damage Through a Simulated RPV Wall - 01 January 2008

STP46566S: Phosphorus Segregation and Intergranular Embrittlement in Thermally Aged and Neutron Irradiated Reactor Pressure Vessel Steels - 01 January 2008

STP46567S: Information Fusion Embrittlement Models for U.S. Power Reactor Pressure Vessel Steels - 01 January 2008

STP41649S: Performance Evaluation of “Duplex Hardened” Bearings for Advanced Turbine Engine Applications - 01 January 2007

STP45528S: Temperature Dependence and Variability of Fracture Toughness in the Transition Regime for A508 Grade 4N Pressure Vessel Steel - 01 January 2007

STP45530S: Prediction of the Shape of the KJ Ductile-to-Brittle Transition Temperature Curve for Ferritic Pressure Vessel Steels Using the Material's Resistance to Crack Extension KJ versus Δa Curve - 01 January 2007

STP45432S: Measurement of Helium Generation in AISI 304 Reflector and Blanket Assemblies after Long-term Irradiation in EBR-II - 01 January 2007

STP1490-EB: Reactor Dosimetry: 12th International Symposium - 01 January 2007

STP45433S: Verification of MultiTrans Calculations by the VENUS-3 Benchmark Experiment - 01 January 2007

STP45421S: Reactor Dosimetry Issues During Justification of Extension of Service Life of Nonrestorable Equipment of Russian VVER - 01 January 2007

STP45434S: The Neutron Spectrum of NBS-1 - 01 January 2007

STP45435S: Radiation Dosimetry in the BNCT Patient Treatment Room at the Brookhaven Medical Research Reactor - 01 January 2007

STP45436S: TRIM Modeling of Displacement Damage in SiC for Monoenergetic Neutrons - 01 January 2007

STP45437S: Thermal and Epithermal fluence Rate Measurements in Multipurpose Reactors: Application of a Least-Squares Fitting Code RESDET to Obtain Thermal and Epithermal Fluence Rates from Measured Reaction Rates - 01 January 2007

STP45438S: Neutron and Photon Dosimetry at the LR-0 Reactor Using Paired Detectors - 01 January 2007

STP45439S: Survey of the Latest Evaluated Nuclear Data - 01 January 2007

STP45440S: Gas Production in Reactor Materials - 01 January 2007

STP45441S: Dosimetry Requirements for Pressure Vessel Steels Toughness Curve in the Ductile to Brittle Range - 01 January 2007

STP45442S: Mesh Tally Radiation Damage Calculations and Application to the SNS Target System - 01 January 2007

STP45443S: Attenuation of Radiation Damage and Neutron Field in Reactor Pressure Vessel Wall - 01 January 2007

STP45444S: An International Evaluation of the Neutron Cross Section Standards - 01 January 2007

STP45422S: Validation of the Neutron Fluence Calculation on the VVER-440 RPV support structure - 01 January 2007

STP45445S: Precision Neutron Total Cross-Sectional Measurements for Natural Carbon at Reactor Neutron-Filtered Beams - 01 January 2007

STP45446S: Spallation Radiation Damage Calculations and Database: Cross-Section Discrepancies between the Codes - 01 January 2007

STP45447S: Proton Induced Activation in Mercury: Comparison of Measurements and Calculations - 01 January 2007

STP45448S: Measurements and Monte Carlo Calculations of Gamma and Neutron Flux Spectra Inside and Behind Iron/Steel/Water Configurations - 01 January 2007

STP45449S: Advances in Calculation of Fluence to Reactor Structures - 01 January 2007

STP45450S: Deterministic and Monte Carlo Neutron Transport Calculation for Greifswald-1 and Comparison with Ex-vessel Measured Data - 01 January 2007

STP45451S: Coarse-Mesh Adjoint Biasing of a Monte Carlo Dose Calculation - 01 January 2007

STP45452S: Analysis of the VENUS-3 PWR Pressure Vessel Surveillance Benchmark Using TRIPOLI-4.3 Monte Carlo Code - 01 January 2007

STP45423S: Reactor Dosimetry Study of the Rhode Island Nuclear Science Center - 01 January 2007

STP45453S: Influence of the Multigroup Approximation on VVER-1000 RPV Neutron/Gamma Flux Calculation - 01 January 2007

STP45454S: A New Derivation of the Perturbation Operator Used in MCNP - 01 January 2007

STP45455S: Calculation of Neutron Fluxes for Radioactive Inventory Assessment of Magnox Power Plant - 01 January 2007

STP45456S: Extensive Revision of the Kernel-Based PREVIEW Program and Its Input Data - 01 January 2007

STP45457S: Investigation of Radiation Transport Modeling Trends in the WSMR Fast Burst Reactor Environments - 01 January 2007

STP45458S: Coupled Neutron-Gamma Calculations for the LR-0 Experimental Benchmark - 01 January 2007

STP45459S: Use of CPXSD for Generation of Effective Fast Multigroup Libraries for Pressure Vessel Fluence Calculations - 01 January 2007

STP45460S: Benchmarking of PENTRAN-SSN Parallel Transport Code and FAST Preconditioning Algorithm Using the VENUS-2 MOX-Fueled Benchmark Problem - 01 January 2007

STP45461S: Sensitivity Analysis and Neutron Fluence Adjustment for VVER-440 RPV - 01 January 2007

STP45462S: Generalized Linear Least-Squares Adjustment, Revisited - 01 January 2007

STP45463S: Retrospective Measurement of Neutron Activation within the Pressure Circuit Steelwork of a Magnox Reactor and Comparison with Prediction - 01 January 2007

STP45424S: Comparison of the Results of the Calculational and Experimental VVER-440 Pressure Vessel Dosimetry at Paks NPP - 01 January 2007

STP45464S: Comparison of Predicted and Measured Helium Production in U.S. BWR Reactors - 01 January 2007

STP45465S: Shielding Calculations for the Upgrade of the HFIR HB 2 Beam Line - 01 January 2007

STP45466S: An Approach to Determining the Uncertainty in Reactor Test Objects Using Deterministic and Monte Carlo Methods - 01 January 2007

STP45467S: Development of a Silicon Calorimeter for Dosimetry Applications in a Water-Moderated Reactor - 01 January 2007

STP45468S: Measurement and Calculation of WWER-440 Pressure Vessel Templates Activity for Support of Vessel Dosimetry - 01 January 2007

STP45420S: Feasibility Study on a Simple Method of Retrospective Neutron Dosimetry for Reactor Internals and Reactor Vessel - 01 January 2007

STP45470S: Retrospective Dosimetry of Fast Neutrons Focused on the Reactions 93Nb(n,n')93Nbm and 54Fe(n,p)54Mn - 01 January 2007

STP45471S: Spent Fuel Monitoring with Silicon Carbide Semiconductor Neutron/Gamma Detectors - 01 January 2007

STP45472S: Digital Multiparameter System for Characterizing the Neutron-Gamma Field in the LR-O Experimental Reactor - 01 January 2007

STP45425S: Characterizing the Time- and Energy-Dependent Reactor n/γ Environment - 01 January 2007

STP45474S: Application of a Silicon Calorimeter in Fast Burst Reactor Environments - 01 January 2007

STP45475S: The Validity of the Use of Equivalent DIDO Nickel Dose for Graphite Dosimetry - 01 January 2007

STP45476S: Neutron Damage in SiC Semiconductor Radiation Detectors in the GT-MHR - 01 January 2007

STP45477S: Evaluation of Diamond Detectors for Fast Neutron Fluence Measurements in WWER-1000 Surveillance Assemblies - 01 January 2007

STP45478S: A New Methodology for Adjustment of Iron Scattering Cross Sections Using Time-of-Flight Spectroscopy - 01 January 2007

STP45479S: Reactor Dosimetry with Niobium - 01 January 2007

STP45426S: Determination of Adjusted Neutron Spectra in Different MUSE Configurations by Unfolding Techniques - 01 January 2007

STP45427S: Characterization of Neutron Fields Using MCNP in the Experimental Fast Reactor JOYO - 01 January 2007

STP45428S: Benchmark on the 3-D VENUS-2 MOX-Fueled Reactor Dosimetry Calculations by DANTSYS Code System - 01 January 2007

STP45429S: Experimental and Calculation Investigations of the Space-Energy Neutron and Photon Distribution in the Vicinity of Reactor Pressure Vessel and Surveillance Specimen Box of New Type in the WWER-1000 Mock-Up - 01 January 2007

STP45430S: Characterization of the Neutron Field in the HSSI Reusable Irradiation Facility at the Ford Nuclear Reactor - 01 January 2007

STP45431S: Benchmark Experiments/Calculations of Neutron Environments in the Annular Core Research Reactor - 01 January 2007

STP37572S: Development of Fuel Clad Materials for High Burn-up Operation of LWR - 01 January 2006

STP1475-EB: Effects of Radiation on Materials: 22nd Symposium - 01 January 2006

STP37573S: Small Angle Neutron Scattering Study of Irradiated Martensitic Steels: Relation Between Microstructural Evolution and Hardening - 01 January 2006

STP37574S: Radiation Resistance of Advanced Ferritic-Martensitic Steel HCM12A - 01 January 2006

STP37575S: Microstructural and Mechanical Characterization of Radiation Effects in Model Reactor Pressure Vessel Steels - 01 January 2006

STP37565S: Radiation-Induced Stress Relaxation of Welded Type 304 Stainless Steel Evaluated by Neutron Diffraction - 01 January 2006

STP37576S: Effects of Neutron Irradiation on Precipitation in Reactor Pressure Vessel Steels - 01 January 2006

STP37577S: Radiation- and Thermally-Induced Phosphorus Inter-Granular Segregation in Pressure Vessel Steels - 01 January 2006

STP37578S: Fracture Toughness, Thermo-Electric Power, and Atom Probe Investigations of JRQ Steel in I, IA, IAR, and IARA Conditions - 01 January 2006

STP37579S: Assessment of Neutron Irradiation-Induced Grain Boundary Embrittlement by Phosphorous Segregation in a Reactor Pressure Vessel Steel - 01 January 2006

STP37580S: Effects of Neutron Dose, Dose Rate, and Irradiation Temperature on the Irradiation Embrittlement of a Low-Copper Reactor Pressure Vessel Steel - 01 January 2006

STP37581S: Mechanical Property Changes in Reactor Vessel Materials Thermally Aged for 209000 H at 282 °C - 01 January 2006

STP37582S: Recent Surveillance Data and a Revised Embrittlement Correlation - 01 January 2006

STP37583S: Use of Broken Charpy V-notch Specimens from a Surveillance Program for Fracture Toughness Determination - 01 January 2006

STP37584S: Dynamic Finite Element Modeling of Fracture in Charpy V-Notch Specimens of Weld Material 72W - 01 January 2006

STP37585S: Effects of Proton Irradiation on Reactor Pressure Vessel Steel and Its Model Alloys - 01 January 2006

STP37586S: Correlated Formation and Stability of SIA Loops and Stacking Fault Tetrahedra in High Energy Displacement Cascades in Copper - 01 January 2006

STP37587S: Atomic-Scale Simulation of Defect Cluster Formation in High-Energy Displacement Cascades in Zirconium - 01 January 2006

STP37588S: Flow Localization Processes in Austenitic Alloys - 01 January 2006

STP37589S: Deformation Mechanism Maps of Unirradiated and Irradiated V-4Cr-4Ti - 01 January 2006

STP37566S: Low Strain-Rate Microstructural Deformation Behavior in 316 Stainless Steel Irradiated in EBR-II - 01 January 2006

STP37591S: Microstructure Evolution in ZrC Irradiated with Kr ions - 01 January 2006

STP37592S: Mechanical Properties of Cubic Silicon Carbide after Neutron Irradiation at Elevated Temperatures - 01 January 2006

STP37593S: Creep-Fatigue Behavior in High Strength Copper Alloys - 01 January 2006

STP37594S: Tensile, Flexural, and Shear Properties of Neutron Irradiated SiC/SiC Composites with Different Fiber-Matrix Interfaces - 01 January 2006

STP37564S: Behavior of Irradiated Type 316 Stainless Steels under Low- Strain-Rate Tensile Conditions - 01 January 2006

STP37567S: Neutron Flux Effect on the Irradiation Hardening of Type 304 Stainless Steel - 01 January 2006

STP37568S: Modeling the Effects of Oversize Solute Additions on Radiation-Induced Segregation in Austenitic Stainless Steels - 01 January 2006

STP37569S: Post-Irradiation Tensile Behavior and Residual Activity of Several Ferritic/Martensitic and Austenitic Steels Irradiated in Osiris Reactor at 325°C up to 9 dpa - 01 January 2006

STP37570S: The Role of Grain Boundary Engineering on the High Temperature Creep of Ferritic-Martensitic Alloy T91 - 01 January 2006

STP37571S: Extrapolation of Fracture Toughness Data for HT9 Irradiated at 360–390°C - 01 January 2006

STP37504S: On Secondary β-Nb Phase Precipitation within Primary α-Zr Phase in Zr-Nb Alloys During Tensile Deformation - 01 January 2005

STP1467-EB: Zirconium in the Nuclear Industry: Fourteenth International Symposium - 01 January 2005

STP37505S: Microstructure and Phase Control in Zr-Fe-Cr-Ni Alloys: Thermodynamic and Kinetic Aspects - 01 January 2005

STP37506S: Modeling of the Simultaneous Evolution of Vacancy and Interstitial Dislocation Loops in hcp Metals Under Irradiation - 01 January 2005

STP37507S: Microstructural Stability of M5™ Alloy Irradiated up to High Neutron Fluences - 01 January 2005

STP37508S: Microstructure and Growth Mechanism of Oxide Layers Formed on Zr Alloys Studied with Micro-Beam Synchrotron Radiation - 01 January 2005

STP37510S: Temperature and Strain Rate Effects on Zr-1%Nb Alloy Deformation - 01 January 2005

STP37511S: Phase Composition, Structure, and Plastic Deformation Localization in Zr1%Nb alloys - 01 January 2005

STP37512S: The Effect of Beta-Quenching in Final Dimension on the Irradiation Growth of Tubes and Channels - 01 January 2005

STP37513S: Destruction of Crystallographic Texture in Zirconium Alloy Tubes - 01 January 2005

STP37514S: Improved ZIRLO™ Cladding Performance through Chemistry and Process Modifications - 01 January 2005

STP37515S: Role of Iron for Hydrogen Absorption Mechanism in Zirconium Alloys - 01 January 2005

STP37516S: In-Situ Studies of the Oxide Film Properties on BWR Fuel Cladding Materials - 01 January 2005

STP37517S: The Correlation Between Microstructures and in-BWR Corrosion Behavior of Highly Irradiated Zr-based Alloys - 01 January 2005

STP37500S: ZIRLO™ — An Alloy Development Success - 01 January 2005

STP37518S: Effect of Alloying Elements and Impurities on in-BWR Corrosion of Zirconium Alloys - 01 January 2005

STP37519S: In-Core Tests of Effects of BWR Water Chemistry Impurities on Zircaloy Corrosion - 01 January 2005

STP37520S: Shadow Corrosion Mechanism of Zircaloy - 01 January 2005

STP37521S: TEM Examinations of the Metal-Oxide Interface of Zirconium Based Alloys Irradiated in a Pressurized Water Reactor - 01 January 2005

STP37522S: Comparison of the High Burn-Up Corrosion on M5 and Low Tin Zircaloy-4 - 01 January 2005

STP37523S: The Effect of Duplex Cladding Outer Component Tin Content on Corrosion, Hydrogen Pick-up, and Hydride Distribution at Very High Burnup - 01 January 2005

STP37502S: Plastic Deformation of Irradiated Zirconium Alloys: TEM Investigations and Micro-Mechanical Modeling - 01 January 2005

STP37524S: Predicting Oxidation and Deuterium Ingress for Zr-2.5Nb CANDU Pressure Tubes - 01 January 2005

STP37525S: Inhibitors for Reducing Hydrogen Ingress During Corrosion of Zirconium Alloys - 01 January 2005

STP37526S: Identification of Crystalline Behavior on Macroscopic Response and Local Strain Field Analysis: Application to Alpha Zirconium Alloys - 01 January 2005

STP37527S: Ductility of Zircaloy-4 Fuel Cladding and Guide Tubes at High Fluences - 01 January 2005

STP37528S: Thermal Creep of Irradiated Zircaloy Cladding - 01 January 2005

STP37529S: Use of the Irradiation-Thermal Creep Model of Zr-1 % Nb Alloy Cladding Tubes to Describe Dimensional Changes of VVER Fuel Rods - 01 January 2005

STP37530S: Influence of Structure—Phase State of Nb Containing Zr Alloys on Irradiation-Induced Growth - 01 January 2005

STP37531S: Damage Dependence of Irradiation Deformation of Zr-2.5Nb Pressure Tubes - 01 January 2005

STP37532S: Delayed Hydrogen Cracking Velocity and J-Integral Measurements on Irradiated BWR Cladding - 01 January 2005

STP37533S: Overload Fracture of Flaw Tip Hydrides in Zr-2.5Nb Pressure Tubes - 01 January 2005

STP37534S: Effect of Irradiation on the Fracture Properties of Zr-2.5Nb Pressure Tubes at the End of Design Life - 01 January 2005

STP37535S: Effect of Fabrication Variables on Irradiation Response of Crack Growth Resistance of Zr-2.5Nb - 01 January 2005

STP37536S: Fretting-Wear Behavior of Zircaloy-4, OPTIN™, and ZIRLO™ Fuel Rods and Grid Supports under Various Autoclave and Hydraulic Loop Endurance Test Conditions - 01 January 2005

STP37503S: Study of Nb and Fe Precipitation in α-Phase Temperature Range (400 to 550°C) in Zr-Nb-(Fe-Sn) Alloys - 01 January 2005

STP37537S: Failure of Hydrided Zircaloy-4 Under Equal-Biaxial and Plane-Strain Tensile Deformation - 01 January 2005

STP37538S: Mechanical Properties of Zircaloy-4 PWR Fuel Cladding with Burnup 54-64MWd/kgU and Implications for RIA Behavior - 01 January 2005

STP37539S: The Effect of Liner Component Iron Content on Cladding Corrosion, Hydriding, and PCI Resistance - 01 January 2005

STP37540S: Influence of Long Service Exposures on the Thermal-Mechanical Behavior of Zy-4 and M5™ Alloys in LOCA Conditions - 01 January 2005

STP11222S: Martensitic Transformations in Neutron Irradiated and Helium Implanted Stainless Steels - 01 January 2004

STP1447-EB: Effects of Radiation on Materials: 21st International Symposium - 01 January 2004

STP11223S: Fracture Toughness and Atom Probe Characterization of a Highly Embrittled RPV Weld - 01 January 2004

STP11224S: On the Mechanism of Irradiation Embrittlement Enhancement in Reactor Pressure Vessel Steels at High Neutron Fluences - 01 January 2004

STP11225S: Irradiation and Post-Annealing Reirradiation Effects on Fracture Toughness of RPV Steel Heat JRQ - 01 January 2004

STP11215S: Study on Ductile Fracture Strain and Fracture Toughness of Irradiated Austenitic Stainless Steels - 01 January 2004

STP11226S: Dependence of Re-embrittlement Rate After Annealing on the Copper, Nickel and Phosphorus Contents in Model Alloys - 01 January 2004

STP11227S: Evaluation of Irradiation Embrittlement of A508 Gr 4N and Comparison to Other Low-Alloy Steels - 01 January 2004

STP11228S: Microstructural Aspects of Irradiation Damage in A508 Gr 4N Forging Steel: Composition and Flux Effects - 01 January 2004

STP11229S: Effect of Stress Relief Time on the Transition Temperature of Linde 80 Welds - 01 January 2004

STP11230S: Critical Review of Through-Wall Attenuation of Mechanical Properties in RPV Steels - 01 January 2004

STP11231S: A Mechanistically-Guided Charpy Embrittlement Correlation for Reactor Pressure Vessel Integrity Assessment - 01 January 2004

STP11232S: Development of RPV Embrittlement Evaluation Technology for Charpy Upper Shelf Region - 01 January 2004

STP11233S: Master Curve of Irradiated JRQ Material - 01 January 2004

STP11234S: Development of International Guidelines for Application of the Master Curve Approach to Reactor Pressure Vessel Integrity - 01 January 2004

STP11235S: The Technical Foundations of a Unified Adjusted Reference Temperature for RPV Fracture Toughness - 01 January 2004

STP11236S: A Statistical Analysis of the Effect of Neutron Irradiation Dose and Dose Spectrum on Changes of Charpy Impact Energy for C-Mn Steels - 01 January 2004

STP11237S: The Effect of Neutron Flux on Radiation-Induced Embrittlement in Reactor Pressure Vessel Steels - 01 January 2004

STP11216S: Investigation of Microstructure and Mechanical Properties of 18Cr-10Ni-Ti Steel Irradiated in the Core of VVER-1000 Reactor - 01 January 2004

STP11238S: Hardening Mechanisms in Ferritic/Martensitic Steels - 01 January 2004

STP11239S: Effects of Copper Content on the Tensile Properties of Iron-Copper Alloys - 01 January 2004

STP11240S: Irradiation Hardening and Microstructural Evolution in Fe-Cu Model Alloys - 01 January 2004

STP11241S: Effect of Heat Treatment and Tantalum on Microstructure and Mechanical Properties of Fe-9Cr-2W-0.25V Steel - 01 January 2004

STP11242S: Oxide Particle Stability in Oxide Dispersion Strengthened Ferritic Steels During Neutron Irradiation - 01 January 2004

STP11214S: Properties of 20 % Cold-Worked 316 Stainless Steel Irradiated at Low Dose Rate - 01 January 2004

STP11243S: Examination of Postirradiation Deformation Microstructures in F82H - 01 January 2004

STP11244S: Fracture Toughness Characterization of Irradiated F82H in the Transition Region - 01 January 2004

STP11245S: Incubation Period for Void Swelling and Its Dependence on Temperature, Dose Rate, and Dislocation Structure Evolution - 01 January 2004

STP11246S: Determination of the Lower Temperature Limit of Void Swelling of Stainless Steels at PWR-Relevant Displacement Rates - 01 January 2004

STP11247S: Dependence of Maximum Swelling Temperature on Damage Dose in Cold Worked 16Cr-15Ni-2Mo-1Mn Cladding Irradiated in BN-600 - 01 January 2004

STP11248S: Stress and Temperature Dependence of Irradiation Creep of Selected FCC and BCC Steels at Low Swelling - 01 January 2004

STP11249S: Irradiation Creep and Swelling of Russian Ferritic-Martensitic Steels Irradiated to Very High Exposures in the BN-350 Fast Reactor at 305–335°C - 01 January 2004

STP11217S: Influence of Oversized Solute Additions on Radiation-Induced Microstructure and Microchemistry in Austenitic Stainless Steel - 01 January 2004

STP11250S: Kinetics of Helium Bubble Formation in Nuclear and Structural Materials - 01 January 2004

STP11251S: Bubble Microstructures in Helium Injected Palladium Foils - 01 January 2004

STP11252S: Fatigue Response and Life Prediction of Selected Reactor Materials - 01 January 2004

STP11253S: Detection of Radiation-Enhanced Diffusion by Means of Neutron-Irradiated Diffusion Couples of Fe-Cr-Ni System - 01 January 2004

STP11254S: Surprisingly Large Generation and Retention of Helium and Hydrogen in Pure Nickel Irradiated at High Temperatures and High Neutron Exposures - 01 January 2004

STP11255S: The Influence of Pre-Irradiation Heat Treatments on Thermal Non-Equilibrium and Radiation-Induced Segregation Behavior in Model Austenitic Stainless Steel Alloys - 01 January 2004

STP11256S: Inter-Granular Phosphorus Segregation in Ferritic Steels - 01 January 2004

STP11257S: Grain Boundary Phosphorous Segregation and Its Influence on the Ductile Brittle Transition Temperature in Reactor Pressure Vessel Steels - 01 January 2004

STP11218S: Solute Addition Effect for Fe-15Cr-20Ni Austenitic Steels Irradiated in Joyo - 01 January 2004

STP11258S: The Modeling of Radiation-Induced Phosphorus Segregation at Point Defect Sinks in Dilute Fe-P Alloys - 01 January 2004

STP11259S: Irradiation Induced Vacancy-Cu Aggregations in Fe-Cu Model Alloys of Reactor Pressure Vessel Steels Studied by Positron Annihilation - 01 January 2004

STP11260S: Heavy Ion Fluence Measurements Based on Radiation Effects Generated in CTA Foils - 01 January 2004

STP11261S: Tensile Property Estimates Obtained Using a Low Compliance Shear Punch Test Fixture - 01 January 2004

STP11262S: Revisiting the Use of SiC as a Post Irradiation Temperature Monitor - 01 January 2004

STP11263S: New Methodologies for Developing Radiation Embrittlement Models and Trend Curves of the Charpy Impact Test Data - 01 January 2004

STP11264S: Mechanical and Structural Property Changes of Monolithic SiC and Advanced SiC/SiC Composites due to Low Temperature He+-Ion Irradiation and Post-Irradiation High Temperature Annealing - 01 January 2004

STP11219S: The Effect of Void Swelling on Electrical Resistance and Elastic Moduli in Austenitic Steels - 01 January 2004

STP11265S: Precipitation and Amorphization in Boron Carbide Irradiated by High Energy Helium Ions - 01 January 2004

STP11266S: Effects of Pu Decay on a Sodalite Based Ceramic Waste Form - 01 January 2004

STP11267S: Changes in Mechanical Properties of High-Purity V-4Cr-4Ti-Si, Al, Y Alloys after Neutron Irradiation at Relatively Low Temperatures - 01 January 2004

STP11268S: Creep Deformation in V-4Cr-4Ti in a Low-Oxygen Lithium Environment - 01 January 2004

STP11269S: Varying Temperature Irradiation Effects of V-4Cr-4Ti Alloy with Small Addition of Si, Al and Y - 01 January 2004

STP11270S: Peculiarities of Structural and Behavioral Changes of Some Zirconium Alloys at Damage Doses of Up to 50 dpa - 01 January 2004

STP11271S: Effect of Ion Irradiation on Microstructure and Hardness in Zircaloy-4 - 01 January 2004

STP11272S: Microstructure Response in Copper and Copper Alloys Irradiated with Fission Neutrons with Controlled Temperature Variations - 01 January 2004

STP11220S: The Role of Fine Defect Clusters in Irradiation-Assisted Stress Corrosion Cracking of Proton-Irradiated 304 Stainless Steel - 01 January 2004

STP11221S: The Effect of Hardening Source in Proton Irradiation-Assisted Stress Corrosion Cracking of Cold Worked Type 304 Stainless Steel - 01 January 2004

STP11286S: Preliminary Results of the United States Nuclear Regulatory Commission's Pressurized Thermal Shock Rule Reevaluation Project - 01 January 2004

STP11288S: A Software Framework for Probabilistic Fatigue Life Assessment of Gas Turbine Engine Rotors - 01 January 2004

STP11072S: Experiences and Modeling of Hydrogen Cracking in a Thick-Walled Pressure Vessel - 01 January 2003

STP10765S: Development of Test Methods for High Temperature Fretting of Turbine Materials Subjected to Engine-Type Loading - 01 January 2003

STP11667S: An X-Specimen Test for Determination of Thin-Walled Tube Fracture Toughness - 01 January 2002

STP10635S: Detection and Characterization of Imperfections in Composite Pressure Vessels - 01 January 2002

STP10817S: Finite Element Simulations and Empirical Correlation for Charpy-V and Subsize Charpy Tests on an Unirradiated Low-Alloy RPV Ferritic Steel - 01 January 2002

STP1418-EB: Small Specimen Test Techniques: Fourth Volume - 01 January 2002

STP10818S: Correlation Between Subsize and Full-size Charpy Impact Properties of Neutron-Irradiated Reactor Pressure Vessel Steels - 01 January 2002

STP10819S: Application of the Reconstituted Subsize Specimens for Assessment of Irradiation Embrittlement of RPV Steels - 01 January 2002

STP10820S: Evaluation of Fatigue Properties with Miniature Hourglass Specimen - 01 January 2002

STP10811S: Validation of Miniature Fracture Toughness Specimens for Material Surveillance - 01 January 2002

STP10821S: Mechanical Property Testing of Irradiated Zircaloy Cladding Under Reactor Transient Conditions - 01 January 2002

STP10822S: In-Beam Fatigue Response of a Low Activation Ferritic Steel at 60°C - 01 January 2002

STP10823S: On the Relation Between Engineering Load-Displacement Curves and True Stress Strain Behavior in Tests of Flat Tensile Specimens - 01 January 2002

STP10824S: Validation of a Miniature Tensile Strength Measurement System - 01 January 2002

STP10825S: Component-Based Test Specimen Design - 01 January 2002

STP10826S: A Method to Study Deformation Mechanisms in Ion-irradiated Steels Using a Disk Bend Test Technique - 01 January 2002

STP10827S: Small Specimen Procedures for Determination of Deformation Maps - 01 January 2002

STP10828S: Specimen Size Effects on Tensile Properties of 2D/3D SiC/SiC Composites - 01 January 2002

STP10829S: A Finite Element Study Relating Load-Penetration Curves and Indentation Topography to Yield and Post-Yield Constitutive Behavior - 01 January 2002

STP10830S: Subsize Specimens for Fatigue Crack Growth Rate Testing of Metallic Materials - 01 January 2002

STP10831S: The Effect of Test Machine Compliance on the Measured Shear Punch Yield Stress as Predicted Using Finite Element Analysis - 01 January 2002

STP10812S: Examination on Fracture Resistance of F82H Steel and Performance of Small Specimens in Transition and Ductile Regimes - 01 January 2002

STP10832S: Small Punch Test : EPRI-CEA Finite Element Simulation Benchmark and Inverse Method for the Estimation of Elastic Plastic Behavior - 01 January 2002

STP10833S: The Effect of Specimen Thickness and Grainsize on Mechanical Properties Obtained from the Shear Punch Test - 01 January 2002

STP10834S: Determination of Mechanical Property Gradients in Heat-Affected Zones of Ferritic Steel Weldments by Shear-Punch Tests - 01 January 2002

STP10810S: Fracture Toughness Measurements in the Transition Region Using Sub-Size Precracked Charpy and Cylindrical Bar Specimens - 01 January 2002

STP10835S: RESQUE: Reconstitution Techniques Qualification & Evaluation to Study Ageing Phenomena of Nuclear Pressure Vessel Materials - 01 January 2002

STP10836S: RESQUE: Determination of the Lowest Acceptable Insert Length for Reconstituted Cv-impact and Precracked Cv Specimen - 01 January 2002

STP10837S: RESQUE: Validation of Specimen Reconstitution with Temperature Measurements and Comparative Testing with Irradiated Materials - 01 January 2002

STP10838S: Selection of the Optimum Irradiation Fluence to Assess Annealing during Reconstitution of Charpy Impact Specimens - 01 January 2002

STP10839S: Reconstitution of Charpy-V Specimens with CO2 Laser Welding - 01 January 2002

STP10840S: RESQUE: Dependence of Test Results on Reconstituted Specimens with Tolerance Deviations and Variation of End Block Materials - 01 January 2002

STP10813S: A Study of Specimen Size Effects on the Initiation Toughness and Tearing Resistance of an A533B-1 Steel - 01 January 2002

STP10814S: Preferable Initial Crack Length for Fracture Toughness Evaluation Using sub-sized Bend Specimens - 01 January 2002

STP10815S: The Determination of Initiation Toughness of an A533B-1 Steel using Circumferentially-Cracked Bar (CCB) Specimens - 01 January 2002

STP10816S: Evaluation of Standard Charpy Impact Properties with Subsized Specimens - 01 January 2002

STP11386S: Alternative Zr Alloys with Irradiation Resistant Precipitates for High Burnup BWR Application - 01 January 2002

STP1423-EB: Zirconium in the Nuclear Industry: Thirteenth International Symposium - 01 January 2002

STP11387S: Mössbauer Investigations of the Chemical States of Tin and Iron Atoms in Zirconium Alloy Oxide Film - 01 January 2002

STP11388S: Chemical State Analysis of Sn and Fe in ZrO2 by Mössbauer Spectroscopy - 01 January 2002

STP11389S: The Role of Lithium and Boron on the Corrosion of Zircaloy-4 Under Demanding PWR-Type Conditions - 01 January 2002

STP11390S: Study of the Mechanisms Controlling the Oxide Growth Under Irradiation: Characterization of Irradiated Zircaloy-4 and Zr-1Nb-O Oxide Scales - 01 January 2002

STP11381S: Physical Phenomena Concerning Corrosion Under Irradiation of Zr Alloys - 01 January 2002

STP11391S: Hydrogen Evolution and Pickup During the Corrosion of Zirconium Alloys: A Critical Evaluation of the Solid State and Porous Oxide Electrochemistry - 01 January 2002

STP11392S: The Influence of Material Variables on Corrosion and Deuterium Uptake of Zr-2.5Nb Alloy During Irradiation - 01 January 2002

STP11393S: The Cause for Enhanced Corrosion of Zirconium Alloys by Hydrides - 01 January 2002

STP11394S: The Effect of Minor Alloying Elements on Oxidation and Hydrogen Pickup in Zr-2.5Nb - 01 January 2002

STP11395S: Role of Microchemistry and Microstructure on Variability in Corrosion and Deuterium Uptake of Zr-2.5Nb Pressure Tube Material - 01 January 2002

STP11396S: Temperature and Hydrogen Concentration Limits for Delayed Hydride Cracking in Irradiated Zircaloy - 01 January 2002

STP11382S: Role of the Second-Phase Particles in Zirconium Binary Alloys - 01 January 2002

STP11397S: Experimental Study and Preliminary Thermodynamic Calculations of the Pseudo-Ternary Zr-Nb-Fe-(O,Sn) System - 01 January 2002

STP11398S: Activated Slip Systems and Localized Straining of Irradiated Zr Alloys in Circumferential Loadings - 01 January 2002

STP11380S: Simulating the Behavior of Zirconium-Alloy Components in Nuclear Reactors - 01 January 2002

STP11399S: Effects of Neutron Irradiation on the Microstructure of Alpha-Annealed Zircaloy-4 - 01 January 2002

STP11400S: Plastic Deformation and Fracture During the Zr1%Nb Tube Production - 01 January 2002

STP11401S: Development of Crystallographic Texture in CANDU Calandria Tubes - 01 January 2002

STP11402S: Impact of Hydrogen on Dimensional Stability of ZIRLO Fuel Assemblies - 01 January 2002

STP11403S: In-PWR Irradiation Performance of Dilute Tin-Zirconium Advanced Alloys - 01 January 2002

STP11404S: Predicting the In-Reactor Mechanical Behavior of Zr-2.5Nb Pressure Tubes from Postirradiation Microstructural Examination Data - 01 January 2002

STP11405S: The Influence of In-Situ Clad Straining on the Corrosion of Zircaloy in a PWR Water Environment - 01 January 2002

STP11406S: Characteristics of Hydride Precipitation and Reorientation in Spent-Fuel Cladding - 01 January 2002

STP11407S: Test Reactor Studies of the Shadow Corrosion Phenomenon - 01 January 2002

STP11383S: Synchrotron Radiation Study of Second-Phase Particles and Alloying Elements in Zirconium Alloys - 01 January 2002

STP11408S: An In-Reactor Simulation Test to Evaluate Root Cause of Secondary Degradation of Defective BWR Fuel Rod - 01 January 2002

STP11409S: The Effect of Short-Term Dry-Out Transients on the Cladding Properties of Fresh and Pre-Irradiated Fuel Rods - 01 January 2002

STP11410S: Effects of Alpha-Beta Transformation on High Temperature (LOCA) Creep behavior of Zr-Alloys - 01 January 2002

STP11411S: Influence of Hydrogen Content on the α/β Phase Transformation Temperatures and on the Thermal-Mechanical Behavior of Zy-4, M4 (ZrSnFeV), and M5™ (ZrNbO) Alloys During the First Phase of LOCA Transient - 01 January 2002

STP11412S: On the Embrittlement of Zircaloy-4 Under RIA-Relevant Conditions - 01 January 2002

STP11413S: Impact of Irradiation Defects Annealing on Long-Term Thermal Creep of Irradiated ircaloy-4 Cladding Tube - 01 January 2002

STP11414S: Influence of Composition and Condition on In-PWR Behavior of Zr-Sn-Nb-FeCrV Alloys - 01 January 2002

STP11415S: Influence of Zirconium Alloy Chemical Composition on Microstructure Formation and Irradiation Induced Growth - 01 January 2002

STP11416S: Quantitative Assessment of Irradiation Effect on Creep and Corrosion Properties of Zr-Base Alloys - 01 January 2002

STP11417S: Variability of In-Reactor Diametral Deformation for Zr-2.5Nb Pressure Tubing - 01 January 2002

STP11384S: The Behavior of Intermetallic Precipitates in Highly Irradiated BWR LTP Cladding - 01 January 2002

STP11418S: About the Mechanisms Governing the Hydrogen Effect on Viscoplasticity of Unirradiated Fully Annealed Zircaloy-4 Sheet - 01 January 2002

STP11419S: Irradiation Creep Behavior of Zr-Base Alloys - 01 January 2002

STP11420S: The Effect of Small Concentrations of Sulfur on the Plasticity of Zirconium Alloys at Intermediate Temperatures - 01 January 2002

STP11385S: Effects of Hydrogen Pickup and Second-Phase Particle Dissolution on the In-Reactor Corrosion Performance of BWR Claddings - 01 January 2002

STP13585S: Analysis of Pressure Vessel Surveillance Dosimetry Inserted into Korean PWR - 01 January 2001

STP1398-EB: Reactor Dosimetry: Radiation Metrology and Assessment - 01 January 2001

STP13586S: Integrity Assessment for Aging Reactor Vessel of Japan's First Generation PWR Plants - 01 January 2001

STP13587S: Measurement of Neutron Flux Distribution for Decommissioning in Tokai Power Station - 01 January 2001

STP13574S: ASTM Standards for Reactor Dosimetry and Pressure Vessel Surveillance - 01 January 2001

STP13588S: Impact of the ENDF/B-VI Cross Sections on the RPV Fluence Determination - 01 January 2001

STP13589S: Factors Affecting Predicted Neutron Dose Rates to Steel Pressure Vessels of Magnox Plant - 01 January 2001

STP13590S: The Attenuation of Neutron Dose Rates through the Steel Pressure Vessels of Magnox Power Plants - 01 January 2001

STP13591S: Assessment of Activation of Concrete Wall for Decommissioning of Nuclear Power Plants - 01 January 2001

STP13592S: Use of SSTRs and a Multi-Component Shield Assembly to Measure Radiation Penetrating the Reactor Biological Shield in the Presence of Radiation Streaming from Other Sources - 01 January 2001

STP13593S: Spectral Unfolding of Mixed Proton/Neutron Fluences in the LANSCE Irradiation Environment - 01 January 2001

STP13594S: Neutron Beam Characterization at the Finnish BNCT Facility — Measurements and Calculations - 01 January 2001

STP13595S: Establishment of Fe-Filtered Neutron Beam Facility and Measurement of the Filtered Neutrons - 01 January 2001

STP13596S: Design and Characterization of a Facility for Fast Neutron Irradiation of Semiconductors at Penn State - 01 January 2001

STP13597S: Comprehensive Nuclear Fuel Dosimetry Program in the OSIRIS Reactor - 01 January 2001

STP13575S: Developments in Reactor Dosimetry in Japan - 01 January 2001

STP13598S: Dosimetry of a GeV Proton-Driven Spallation Neutron Field by the Activation Method - 01 January 2001

STP13599S: The Irradiation Characteristics of the KUR Heavy Water Facility — Neutron Energy Spectra for Several Irradiation Modes - 01 January 2001

STP13600S: Radiation Dosimetry at the BNL High Flux Beam Reactor and Medical Research Reactor - 01 January 2001

STP13601S: Measurement of Neutron Spectrum at HANARO - 01 January 2001

STP13602S: Combining Measurements and 3D Neutron Transport Calculations — A Powerful Tool in Detailed Neutron Dosimetry and Damage Analysis - 01 January 2001

STP13603S: Characterization of Neutron Field for Stainless Steel Irradiation Experiments in JMTR - 01 January 2001

STP13604S: Assessment of the Fission Power Level in Fuel Rods Irradiated in the High Flux Materials Testing Reactor BR2 with the Aid of Fluence Dosimetry and Comparison with Other Methods - 01 January 2001

STP13605S: Local Change of a Neutron Spectrum in the Fast Reactor BOR-60 for Extension of Research Tasks - 01 January 2001

STP13606S: Improvement of Reactor Dosimetry for Irradiation Tests in the Experimental Fast Reactor JOYO - 01 January 2001

STP13607S: Estimation of Low Level Neutron Doses Based on Neutron Spectra in the Vicinity of a Nuclear Reactor - 01 January 2001

STP13608S: Conceptual Neutronics Design of “Neutron Factory” as a Future Plan on Neutron Source in Kyoto University Research Reactor Institute (KURRI) - 01 January 2001

STP13609S: Results from the NIST Round Robin Test of Fissionable Dosimeters in a Reactor Leakage Spectrum - 01 January 2001

STP13576S: French PWR Vessel Surveillance Program Dosimetry: Experience Feedback from More than a Hundred Capsules - 01 January 2001

STP13610S: New NEA Benchmarks for Calculating Fast Neutron Fluence in the Reactor Pressure Vessel - 01 January 2001

STP13611S: Database for WWER-1000 Reactor Pressure Vessel IAEA Regional Project RER 4/017 - 01 January 2001

STP13612S: Balakovo-3 Ex-vessel Exercise: Intercomparison of Results - 01 January 2001

STP13613S: Re-analysis of the Experimental Leakage Neutron Spectrum from a Silicon Spherical Shell with Incident 14 MeV Neutrons using Different and Modified Neutron Cross Section Libraries - 01 January 2001

STP13614S: Monte Carlo Calculations of Neutron Fluence Spectra, Activation Measurements, Uncertainty Analysis and Spectrum Adjustment for the KORPUS Dosimetry Benchmark - 01 January 2001

STP13615S: Actual and Potential Measurements of Fission-Rate Ratios in the NIST Iron Sphere - 01 January 2001

STP13616S: Adjustment of the 235U Fission Spectrum - 01 January 2001

STP13617S: Analysis of the ORNL PCA Benchmark Using TORT and BUGLE-96 - 01 January 2001

STP13618S: Development of Calibration Fields of Intermediate Neutrons by Using Several Sources - 01 January 2001

STP13619S: A Study on 14 MeV Neutron Beam Characteristics and its Applications - 01 January 2001

STP13620S: Integral Assessment of the Revised JENDL Dosimetry File - 01 January 2001

STP13577S: Reactor Pressure Vessel Neutron Dosimetry Assessments for UK PWR Plant - 01 January 2001

STP13621S: High Energy Neutron Activation Cross Sections - 01 January 2001

STP13573S: Why Do We Need Dosimetry? - 01 January 2001

STP13622S: SPALLDOS: New Neutron Metrology Cross-Section Library for Use at Spallation Neutron Sources - 01 January 2001

STP13623S: Integral Testing of Spallation Cross Sections for Neutron Dosimetry at 113 and 256 MeV - 01 January 2001

STP13624S: Production of a Dosimetry Cross Section Set Up to 50 MeV - 01 January 2001

STP13625S: Neutron and Non-Neutron Nuclear Data for Radiation Dosimetry - 01 January 2001

STP13626S: New Measurements of the H(n,n)H Angular Distribution - 01 January 2001

STP13627S: Fission Cross Section Measurements of Th-229 and Pa-231 Using Linac-Driven Lead Slowing-Down Spectrometer - 01 January 2001

STP13628S: Measurement of Differential Neutron-Induced Charged-Particle Emission Cross Sections for 5 – 75 MeV Neutrons - 01 January 2001

STP13629S: Fast Neutron Yields Generated from Deuteron Break-up in Low Energy Reactions of Light Nuclei - 01 January 2001

STP13630S: Measurement of the Neutron Capture Cross-Sections for Dy and Hf between 0.001 eV and 50 keV Using Total Energy Absorption Detector - 01 January 2001

STP13578S: Assessment of Neutron Fluence Uncertainty and its Impact on Safety Issues - 01 January 2001

STP13631S: Modeling of BWR for Neutron and Gamma Fields Using PENTRAN™ - 01 January 2001

STP13632S: Activity Determination with High Precision for Component Disposal - 01 January 2001

STP13633S: PV-Surveillance Dosimetry and Adjustment: Review of Several Significant Oral Laws - 01 January 2001

STP13634S: Physically Constrained Adjustment of Calculated Neutron Spectra for Dosimetry and Vessel Locations - 01 January 2001

STP13635S: Algorithm and Computer Code of Group Neutron Spectra Transformation - 01 January 2001

STP13636S: Improved Covariance Analysis and Spectrum Adjustment for VVER-1000 Pressure Vessel Fluences - 01 January 2001

STP13637S: A Parametrized Approach for Unfolding the Neutron Flux Spectrum - 01 January 2001

STP13638S: Accuracy and Parallel Performance of PENTRAN™ Using the VENUS-3 Benchmark Experiment - 01 January 2001

STP13639S: Three Dimensional Neutron Analysis in the Baffle-Former Area of PWR Plant - 01 January 2001

STP13579S: Review of Problems and Requirements in VVER Reactor-Type Pressure Vessel Dosimetry - 01 January 2001

STP13640S: MCBEND — A Fluence Modeling Tool - 01 January 2001

STP13641S: Performance of A3MCNP™ for Calculation of 3-D Neutron Flux Distribution in a BWR Core Shroud - 01 January 2001

STP13642S: Development of 3D MCNP-Based BWR Fluence Computational Software Package: MF3D - 01 January 2001

STP13643S: BWR Neutron Fluence Computations using MF3D - 01 January 2001

STP13644S: Development of Induced Activity Estimation Method for PWR Containment - 01 January 2001

STP13645S: Comparative Analysis of DPA Processed from Current Evaluated Nuclear Data Libraries - 01 January 2001

STP13646S: JENDL PKA/KERMA File for IFMIF Project - 01 January 2001

STP13647S: A Study of Displacement Cross Section in Medium-Energy Region - 01 January 2001

STP13648S: Radiation Hardening in BWR Core Shrouds: Relative Roles of Neutron and Gamma Irradiation - 01 January 2001

STP13649S: Correlating Radiation Exposure with Embrittlement: Comparative Studies of Electron- and Neutron-Irradiated Pressure Vessel Alloys - 01 January 2001

STP13580S: Overview of the Surveillance Dosimetry Activities in Ukraine - 01 January 2001

STP13650S: The PKA Energy Spectrum Analysis of Defect Structures in Neutron Irradiated Metals - 01 January 2001

STP13651S: A Comparison of the NRT Displacement Model and Primary Damage Formation Observed in Molecular Dynamics Cascade Simulations - 01 January 2001

STP13652S: Fusion Neutron Irradiation Effects on Some Electronic Devices - 01 January 2001

STP13653S: Projects AMES Dosimetry and MADAM. Results and Future Activities - 01 January 2001

STP13654S: U.S. NRC Embrittlement Data Base (EDB) - 01 January 2001

STP13655S: Measurement of Eigenvalue Separation in Coupled-Core Systems using Optical Fiber with Scintillator - 01 January 2001

STP13656S: Selective and Prompt Self-Powered Neutron Detectors for Characterization of Mixed Radiation Fields in Reactors - 01 January 2001

STP13657S: Neutron and Gamma Ray Dosimetry in Spent-Fuel Radiation Environments Using Silicon Carbide Semiconductor Radiation Detectors - 01 January 2001

STP13658S: Retrospective Fast Neutron Dosimetry of Nuclear Power Plants by Means of Scraping Samples Using the 93Nb(n,n')93mNb Reaction - 01 January 2001

STP13659S: A Novel Neutron Spectrometer with Response of Wide Energy Range - 01 January 2001

STP13581S: Improved Evaluation of the Atucha-I Ex-Vessel Dosimetry - 01 January 2001

STP13660S: Characterization and Representation of the HPGE Detector Efficiency - 01 January 2001

STP13661S: Accreditation and Certification in Radioactivity Measurement: Experience of the CEA/Reactor Dosimetry Laboratory - 01 January 2001

STP13662S: A Laser Compton-Scattered Photon Source for Potential Calibration of Gamma-Ray Detectors in the Energy Range from 2 to 22 MeV - 01 January 2001

STP13663S: Stilbene Neutron Spectrometer with Spreading of a One Parameter Pulse Shape Discrimination Dynamic Range - 01 January 2001

STP13664S: Use of Reaction 93Nb(n, n')93mNb to Determine Neutron Spectra at Outer PV Surface of WWER-1000 Reactor - 01 January 2001

STP13665S: Experimental Method of Neutron Spectra Determination with Activation Foils - 01 January 2001

STP13666S: Qualifying C8/F9 Spectrum Index Measurements by Using Standard Neutron Fields - 01 January 2001

STP13667S: Metal Discs as Very Low Thermal Neutron Flux Monitors in Reactor Environment - 01 January 2001

STP13668S: Development of a Neutron and Gamma-Ray Flux Distribution Measurement System with Scintillator and Optical Fiber Combination - 01 January 2001

STP13669S: Real-Time Dosimetry Method Using an Imaging Plate - 01 January 2001

STP13582S: Reactor Dosimetry in the Surveillance Program of Kozloduy NPP Reactor Pressure Vessels - 01 January 2001

STP13670S: Application of Accumulative Type ESR-Sensors for Determination of Intensity, Spectral Characteristics and Volume Distribution of Intense Gamma and Neutron Fields - 01 January 2001

STP13671S: Neutron Dosimetry Using Diallyl Phthalate Resin - 01 January 2001

STP13672S: Development of In-Core Monitoring System using Optical Fiber for Advanced Fission Reactor - 01 January 2001

STP13673S: Development and Modeling of Neutron Detectors for In-Core Measurement Requirements in Nuclear Reactors - 01 January 2001

STP13674S: Reduction of Inter-Event Dead Time in Data Acquisition System for Simultaneous Measurement of Neutron Pulse Series in Time and Space - 01 January 2001

STP13675S: A System Design for Measuring Boron Concentration in Pressurized Light Water Reactor Cooling Water - 01 January 2001

STP13583S: Evaluation of the Reactor Dosimetry Results Obtained During the First Ten Years of the RPV Surveillance Program at the NPP Paks - 01 January 2001

STP13584S: Neutron Dosimetry for VVER Reactor Pressure Vessels in the Czech Republic - 01 January 2001

STP10501S: M-ROCLE Diesel and Biodiesel Fuel Lubricity Bench Test - 01 January 2001

STP10529S: Master Curve Evaluation of Irradiated Russian VVER Type Reactor Pressure Vessel Steels - 01 January 2001

STP1405-EB: Effects of Radiation on Materials: 20th International Symposium - 01 January 2001

STP10530S: Fracture Toughness Characterization of 304L and 316L Austenitic Stainless Steels and Alloy 718 After Irradiation in High-Energy, Mixed Proton/Neutron Spectrum - 01 January 2001

STP10531S: Review of Phosphorus Segregation and Intergranular Embrittlement in Reactor Pressure Vessel Steels - 01 January 2001

STP10532S: Modeling of Phosphorus Accumulation on Grain Boundaries in Iron Alloys under Irradiation - 01 January 2001

STP10533S: Grain Boundary Phosphorus Segregation Under Irradiation and Thermal Aging and Its Effect on the Ductile-to-Brittle Transition - 01 January 2001

STP10534S: An Evaluation of Through-Thickness Changes in Primary Damage Production in Commercial Reactor Pressure Vessels - 01 January 2001

STP10535S: Hardness and Microstructure Changes with Thermal Annealing of Neutron-Irradiated Fe-Cu Alloys - 01 January 2001

STP10536S: Effects of Copper Concentration and Neutron Flux on Irradiation Hardening and Microstructure Evolution in Fe-Cu Model Alloys - 01 January 2001

STP10537S: Effects of Neutron Irradiation and Thermal Annealing on Model Alloys Using Positron Annihilation Techniques - 01 January 2001

STP10538S: Microstructural Evolution in High Nickel Submerged Arc Welds - 01 January 2001

STP10523S: Vessel Investigation Program of “CHOOZ A” PWR Reactor after Shutdown - 01 January 2001

STP10539S: An Evaluation of the Effect of Radiation Environment on Linde 80 Reactor Vessel Welds - 01 January 2001

STP10540S: Reirradiation Response Rate of a High-Copper Reactor Pressure Vessel Weld - 01 January 2001

STP10541S: Relation Between Resistivity and Mechanical Properties in Heat Affected Zone of Welded Pressure Vessel Steel - 01 January 2001

STP10542S: Fracture Toughness and Tensile Properties of Irradiated Reactor Pressure Vessel Cladding Material - 01 January 2001

STP10543S: True Characteristics of Strength and Ductility for Neutron-Irradiated Metals and Alloys - 01 January 2001

STP10544S: Investigation of Temper Embrittlement in Reactor Pressure Vessel Steels Following Thermal Aging, Irradiation, and Thermal Annealing - 01 January 2001

STP10545S: Composition Effects on the Radiation Embrittlement of Iron Alloys - 01 January 2001

STP10521S: Review of Current Recommendations from the Recent IAEA Specialists Meeting on Irradiation Effects on Pressure Vessel Steels and its Mitigation - 01 January 2001

STP10546S: The Determination of Bias Factor Stress Dependence from Experimental Data on Irradiation Creep and Stress-Affected Swelling in Austenitic Stainless Steels - 01 January 2001

STP10547S: Swelling and Microstructural Evolution in 316 Stainless Steel Hexagonal Ducts Following Long-Term Irradiation in EBR-II - 01 January 2001

STP10548S: Radiation-Induced Segregation and Void Swelling in 304 Stainless Steel - 01 January 2001

STP10524S: Development of Reconstitution Technology for Surveillance Specimens in Japan Power Engineering and Inspection Corporation - 01 January 2001

STP10549S: Effect of Irradiation Environment of Fast Reactor's Fuel Elements on Void Swelling in P, Ti-Modified 316 Stainless Steel - 01 January 2001

STP10550S: The Swelling Dependence of Cold Worked 16Cr-15Ni-2Mo-lMn Steel on Neutron Irradiation Temperature, Fluence and Damage Rate During Its Use as a Cladding Material in the BN-600 Reactor - 01 January 2001

STP10551S: Tensile Properties of 12% Cold-Worked Type 316 Stainless Steel Irradiated in EBR-II Under Lower-Dose-Rate Conditions to High Fluence - 01 January 2001

STP10552S: Irradiation Creep Deformation of Modified 316 and 15Cr-20Ni Base Austenitic Fuel Elements Irradiated in FFTF - 01 January 2001

STP10553S: Behavior of Different Austenitic Stainless Steels, Conventional, Reduced Activation (RA) and ODS Chromium-Rich Ferritic-Martensitic Steels Under Neutron Irradiation at 325°C in PWR Environment - 01 January 2001

STP10554S: Post-Irradiation Deformation Microstructures in Fe-9Cr - 01 January 2001

STP10555S: Effect of Specimen Size on Fatigue Properties of Reduced Activation Ferritic/Martensitic Steel - 01 January 2001

STP10556S: Correlation Between Creep Properties and Microstructure of Reduced Activation Ferritic/Martensitic Steels - 01 January 2001

STP10557S: Comparison of Thermal Creep and Irradiation Creep of HT9 Pressurized Tubes at Test Temperatures from ∼490°C to 605°C - 01 January 2001

STP10525S: Master Curve Characterization of Irradiation Embrittlement Using Standard and 1/3-Sized Precracked Charpy Specimens - 01 January 2001

STP10558S: Examination of 304L Stainless Steel to 6061-T6 Aluminum Inertia Welded Transition Joints after Irradiation in a Spallation Neutron Spectrum - 01 January 2001

STP10559S: Microstructural Alteration of Structural Alloys by Low Temperature Irradiation with High Energy Protons and Spallation Neutrons - 01 January 2001

STP10560S: Retention of Very High Levels of Helium and Hydrogen Generated in Various Structural Alloys by 800 MeV Protons and Spallation Neutrons - 01 January 2001

STP10561S: The Influence of High Energy Proton Irradiation on the Corrosion of Materials - 01 January 2001

STP10562S: The Effect of High Energy Protons and Neutrons on the Tensile Properties of Materials Selected for the Target and Blanket Components in the Accelerator Production of Tritium Project - 01 January 2001

STP10563S: High-Energy Spallation Neutron Effects on the Tensile Properties of Materials for the Target and Blanket Components for the Accelerator Production of Tritium Project - 01 January 2001

STP10564S: Microstructural Evolution of Reduced Activation and Conventional Martensitic Steels after Thermal Aging and Neutron Irradiation - 01 January 2001

STP10526S: Radiation Damage Assessment by the Use of Dynamic Toughness Measurements on Pre-Cracked Charpy-V Specimens - 01 January 2001

STP10565S: Dimensional Characteristics of Displacement Cascades in Austenitic Steels under Neutron Irradiation at Cryogenic Temperature - 01 January 2001

STP10566S: On the α+γ↔γ-Phase Boundary in Nickel and in Manganese Containing Stainless Steel Alloys - 01 January 2001

STP10567S: Effect of Nickel on Irradiation Hardening and Microstructure Evolution of Proton Irradiated Fe-Cu Alloys - 01 January 2001

STP10568S: Effect of Final Irradiation Temperature and Frequency of Irradiation Temperature Cycles on Microstructural Evolution of Vanadium Alloys - 01 January 2001

STP10569S: Hardening of Vanadium Doped with Nitrogen by Heavy Ion Irradiation and Post-Irradiation Annealing - 01 January 2001

STP10570S: Hydrogen and Helium Gas Formation and their Release Kinetics in Tungsten Rods after Irradiation with 800 MeV Protons - 01 January 2001

STP10571S: The Influence of Temperature, Fluence, Dose Rate, and Helium Production on Defect Accumulation and Swelling in Silicon Carbide - 01 January 2001

STP10572S: Microstructural Stability of SiC/SiC Composites under Dual-Beam Ion Irradiation - 01 January 2001

STP10573S: Molecular Dynamics Simulation of Radiation Damage Production in Cubic Silicon Carbide - 01 January 2001

STP10527S: Comparison of Transition Temperature Shifts Between Static Fracture Toughness and Charpy-v Impact Properties Due to Irradiation and Post-Irradiation Annealing for Japanese A533B-1 Steels - 01 January 2001

STP10574S: Influence of the Reactor and Cyclotron Irradiation on Energy Transformation during Plastic Deformation of Metal Materials - 01 January 2001

STP10575S: Irradiation-Induced Amorphization and Its Recovery Behavior in Cold-Rolled and Aged Ti-Ni Shape Memory Alloys - 01 January 2001

STP10576S: Effect of Mass and Energy on Preferential Amorphization in Polycrystalline Silicon Film during Ion Irradiation - 01 January 2001

STP10577S: Crack Growth Resistance of Irradiated Zr-2.5Nb Pressure Tube Material at Low Hydrogen Levels - 01 January 2001

STP10522S: A Mechanistically-Based Model of Irradiation Damage in Low Alloy Steel Submerged Arc Welds - 01 January 2001

STP10528S: Yield and Toughness Transition Predictions for Irradiated Steels Based on Dislocation Mechanics - 01 January 2001

STP1407-EB: Turbine Lubrication in the 21st Century - 01 January 2001

STP10447S: The Use of a Fire-Resistant Turbine Lubricant: Europe Looks to the Future - 01 January 2001

STP10449S: The Evolution of Base Oil Technology - 01 January 2001

STP10450S: Turbine Oil Quality and Field Application Requirements - 01 January 2001

STP10451S: Performance Advantages of Turbine Oils Formulated with Group II and Group III Basestocks - 01 January 2001

STP10452S: Improved Response of Turbine Oils Based on Group II Hydrocracked Base Oils Compared with Those Based on Solvent Refined Base Oils - 01 January 2001

STP10453S: Performance Advantages of Turbine Oils Formulated with Group II Base Oils - 01 January 2001

STP10454S: Antioxidant Analysis for Monitoring Remaining Useful Life of Turbine Fluids - 01 January 2001

STP14297S: Evolution of Dislocation and Precipitate Structure in Zr Alloys Under Long-Term Irradiation - 01 January 2000

STP1354-EB: Zirconium in the Nuclear Industry: Twelfth International Symposium - 01 January 2000

STP14298S: Effect of Long-Term Irradiation on the Fracture Properties of Zr-2.5Nb Pressure Tubes - 01 January 2000

STP14299S: Post-Irradiation Characterization of Ultra-High-Fluence Zircaloy-2 Plate - 01 January 2000

STP14292S: Effects of Neutron Irradiation on Microstructure and Properties of Zircaloy - 01 January 2000

STP14300S: The Terminal Solid Solubility of Hydrogen in Zirconium Alloys - 01 January 2000

STP14301S: The Long-Range Migration of Hydrogen Through Zircaloy in Response to Tensile and Compressive Stress Gradients - 01 January 2000

STP14302S: Influence of Cladding Microstructure on the Low Enthalpy Failures in RIA Simulation Tests - 01 January 2000

STP14303S: Experiment and Modeling of Advanced Fuel Rod Cladding Behavior Under LOCA Conditions: Alpha-Beta Phase Transformation Kinetics and EDGAR Methodology - 01 January 2000

STP14304S: Behavior of Irradiated Zircaloy-4 Fuel Cladding Under Simulated LOCA Conditions - 01 January 2000

STP14305S: Influence of Texture on the Fracture Toughness of Unirradiated Zircaloy Cladding - 01 January 2000

STP14306S: Degraded Fuel Cladding Fractography and Fracture Behavior - 01 January 2000

STP14293S: Understanding Hydrogen in Zirconium - 01 January 2000

STP14307S: Delayed Hydride Cracking in Irradiated Zircaloy Cladding - 01 January 2000

STP14308S: Size, Geometry, and Material Effects in Fracture Toughness Testing of Irradiated Zr-2.5Nb Pressure Tube Material - 01 January 2000

STP14309S: Failure Mechanisms of Irradiated Zr Alloys Related to PCI: Activated Slip Systems, Localized Strains, and Iodine-Induced Stress Corrosion Cracking - 01 January 2000

STP14310S: Impact of Hydrogen on Plasticity and Creep of Unirradiated Zircaloy-4 Cladding Tubes - 01 January 2000

STP14291S: Microstructure and Properties of Zirconium Alloys in the Absence of Irradiation - 01 January 2000

STP14311S: A New Fabrication Process for Zr-Lined Zircaloy-2 Tubing - 01 January 2000

STP14312S: Zirconium Alloy Cold Pilgering Process Control by Modeling - 01 January 2000

STP14313S: In-Process Investigation of Precipitate Growth in Zirconium Alloys - 01 January 2000

STP14314S: Influence of Composition and Fabrication Process on Out-of-Pile and In-Pile Properties of M5 Alloy - 01 January 2000

STP14294S: Irradiation Creep and Growth Behavior, and Microstructural Evolution of Advanced Zr-Base Alloys - 01 January 2000

STP14315S: Effect of Dilute Alloy Additions of Molybdenum, Niobium, and Vanadium on Zirconium Corrosion - 01 January 2000

STP14316S: E110 Alloy Cladding Tube Properties and Their Interrelation with Alloy Structure-Phase Condition and Impurity Content - 01 January 2000

STP14317S: Contribution to a Better Understanding of the Detrimental Role of Hydrogen on the Corrosion Rate of Zircaloy-4 Cladding Materials - 01 January 2000

STP14318S: Mechanism of Corrosion Rate Degradation Due to Tin - 01 January 2000

STP14319S: Influence of Transition Elements Fe, Cr, and V on Long-Time Corrosion in PWRs - 01 January 2000

STP14320S: Fundamental Study on the Corrosion Mechanism of Zr-0.2Fe, Zr-0.2Cr, and Zr-0.1Fe-0.1Cr Alloys - 01 January 2000

STP14321S: Microstructural Aspects of Corrosion and Hydrogen Ingress in Zr-2.5Nb - 01 January 2000

STP14322S: The Effect of Microstructure on the Corrosion Behavior of Zircaloy-2 in BWRs - 01 January 2000

STP14323S: Impact of Second Phase Particles on BWR Zr-2 Corrosion and Hydriding Performance - 01 January 2000

STP14324S: Corrosion of Electron-Irradiated Zr-2.5Nb and Zircaloy-2 - 01 January 2000

STP14325S: Evaluation of Zircaloy-2 Cladding Corrosion Characteristics by Simulated BWR Corrosion Loop Test - 01 January 2000

STP14295S: Irradiation-Enhanced Deformation of Zr-2.5Nb Tubes at High Neutron Fluences - 01 January 2000

STP14326S: Studies of Zirconium Alloy Corrosion and Hydrogen Uptake During Irradiation - 01 January 2000

STP14327S: Behavior of Lithium and Boron in Irradiated and Unirradiated Oxides Formed on Zircaloy-4 Claddings - 01 January 2000

STP14328S: Contribution to the Understanding of the Effect of the Water Chemistry on the Oxidation Kinetics of Zircaloy-4 Cladding - 01 January 2000

STP14329S: Correlation Between Characteristics of Oxide Films Formed on Zr Alloys in BWRs and Corrosion Performance - 01 January 2000

STP14330S: Electrochemical Examinations in 350°C Water with Respect to the Mechanism of Corrosion-Hydrogen Pickup - 01 January 2000

STP14331S: Hydrogen Transport in the Oxide and Hydrogen Pickup by the Metal During Out- and In-Reactor Corrosion of Zr-2.5Nb Pressure Tube Material - 01 January 2000

STP14296S: High-Fluence Irradiation Growth of Cold-Worked Zr-2.5Nb - 01 January 2000

STP14332S: Stress Distribution Measured by Raman Spectroscopy in Zirconia Films Formed by Oxidation of Zr-Based Alloys - 01 January 2000

STP14333S: Role of Intermetallic Precipitates in Hydrogen Transport through Oxide Films on Zircaloy - 01 January 2000

STP14334S: Multi-Scale Characterization of the Metal-Oxide Interface of Zirconium Alloys - 01 January 2000

STP12447S: Neutron-Induced Evolution of Mechanical Properties of 20% Cold-Worked 316 Stainless Steel as Observed in Both Miniature Tensile and TEM Shear Punch Specimens - 01 January 2000

STP1366-EB: Effects of Radiation on Materials: 19th International Symposium - 01 January 2000

STP12448S: An Investigation into the Origin and Nature of the Slope and x-axis Intercept of the Shear Punch-Tensile Yield Strength Correlation using Finite Element Analysis - 01 January 2000

STP12449S: Thermoelectric Power: A Nondestructive Method for Monitoring Irradiation Effects in Ferritic Steels - 01 January 2000

STP12450S: Design of a Dedicated Electron Beam Facility for Material Treatment - 01 January 2000

STP12451S: Microstructural Examination of Irradiated Beryllium Pebbles - 01 January 2000

STP12452S: Measurement and Calculation of Helium Generation in Beryllium Pebbles Irradiated in EBR-II - 01 January 2000

STP12453S: In-situ Electrical Resistivity Measurement of MgO•Al2O3 Coating under Neutron Irradiation - 01 January 2000

STP12454S: Effect of Ionizing and Displacive Components of Irradiation on the Structural Transformations in Pyrolitic Boron Nitride Ceramics - 01 January 2000

STP12455S: Effect Of Irradiation On Structural Materials In Fusion Reactors - 01 January 2000

STP12456S: Helium/Hydrogen Measurements in High-Energy Proton-Irradiated Tungsten - 01 January 2000

STP12457S: Amorphization of Solids Irradiated by Fast Neutrons - 01 January 2000

STP12458S: Effects of Fast Neutron Irradiation at 80K on Titanium Nickelide - 01 January 2000

STP12459S: Irradiation Aging of Aluminum Alloys - 01 January 2000

STP12460S: Effect of Ion-Irradiation on Phase Transformation in TiNi Shape Memory Alloys - 01 January 2000

STP12461S: Irradiation Growth of Zirconium Alloys at High Neutron Fluences - 01 January 2000

STP12462S: Neutron Irradiation Test of Optical Components for Fusion Reactor - 01 January 2000

STP12463S: Correlation of Hardening and Microstructure of Tantalum Irradiated with Heavy Ions - 01 January 2000

STP12386S: The Effects of Flux on Radiation Embrittlement of Low-Copper Pressure Vessel Steels - 01 January 2000

STP12464S: Improvement of Post Irradiation Ductility of V-Ti-Cr-Si Type Alloys Neutron Irradiated Around 400°C - 01 January 2000

STP12465S: The Influence of Transmutation and Initial Composition on the Microstructural Evolution of Vanadium and V-Cr-Ti Alloys Irradiated in HFIR - 01 January 2000

STP12466S: Neutron Irradiation Induced High Temperature Embrittlement of Pure Copper and High Strength Copper Alloys - 01 January 2000

STP12467S: Effect of Neutron Irradiation on Tensile and Fracture Toughness Properties of Copper Alloys and Their Joints with Stainless Steel - 01 January 2000

STP12387S: Technical Basis for Application of the Master Curve Approach to Reactor Pressure Vessel Integrity Assessment - 01 January 2000

STP12388S: Bias and Precision of To Values Determined Using ASTM Standard E 1921-97 for Nuclear Reactor Pressure Vessel Steels - 01 January 2000

STP12389S: Fracture Toughness of the Ni-Modified A302-B Plate of the BR3 Reactor Pressure Vessel - 01 January 2000

STP12379S: Exploratory Test of 288°C Radiation Resistance of Two USSR-Produced Reactor Pressure Vessel Steels - 01 January 2000

STP12390S: Application of Master Curve Technology to Biaxial and Shallow Crack Fracture Data for A533B Steels - 01 January 2000

STP12391S: Effect of Irradiation on Fracture Toughness in the Transition Range of RPV Steels - 01 January 2000

STP12392S: Supplementary Surveillance Program for Reactor Pressure Vessels of VVER-440/V-213C Type Reactors in NPP Dukovany - 01 January 2000

STP12393S: Irradiation Behavior of Submerged Arc Welding Materials with Different Copper Content - 01 January 2000

STP12394S: Effects of Irradiation on Crack-Arrest Toughness of a Low Upper-Shelf Energy, High-Copper Weld - 01 January 2000

STP12395S: Effect of Location of V-Notch on Neutron Irradiation-Induced Shift in DBTT of HAZ of Welded Pressure Vessel Steel - 01 January 2000

STP12396S: Fracture Toughness Test Results of Precracked Charpy Specimens of Irradiated 73W Weld Material - 01 January 2000

STP12397S: Fracture Toughness of Submerged-Arc Weld Samples from a Decommissioned Magnox Reactor Pressure Vessel: Initial Results - 01 January 2000

STP12398S: Effects of Irradiation and Thermal Annealing on Fracture Toughness of the Midland Reactor Weld WF-70 - 01 January 2000

STP12399S: Irradiation Damage Structure in VVER-440 Steels after Irradiation at Different Temperatures and Post-Irradiation Annealing - 01 January 2000

STP12380S: Analysis of Irradiation Data for A302B and A533B Correlation Monitor Materials - 01 January 2000

STP12400S: Grain Boundary Phosphorus Segregation under Neutron Irradiation and Aging in 2.25Cr1Mo Steel - 01 January 2000

STP12401S: Microstructure of the Neutron Irradiated VVER-type Reactor Pressure Vessel Steels - 01 January 2000

STP12402S: Influence of Thermal Neutrons on the Hardening and Embrittlement of Plate Steels - 01 January 2000

STP12403S: Radiation-Induced Grain Boundary Segregation of Phosphorus in ASME SA533B Ferritic Pressure Vessel Steel - 01 January 2000

STP12404S: Comparison of Observed and Predicted Data on Radiation Induced Grain Boundary Phosphorus Segregation in VVER Type Steels - 01 January 2000

STP12378S: A Comparison of East/West Steels for Pressurized Water Reactors - 01 January 2000

STP12405S: Irradiation, Annealing, and Reirradiation Effects on American and Russian Reactor Pressure Vessel Steels - 01 January 2000

STP12406S: Annealing of a Low Copper Steel: Hardness, SANS, Atom Probe, and Thermoelectric Power Investigations - 01 January 2000

STP12407S: Two-Step Recovery Process of Irradiation Hardening in 1%Ni Doped 9%Cr-2%W Martensitic Steel - 01 January 2000

STP12408S: Application of the Floating Curve Model for Estimation of Re-Irradiation Embrittlement of VVER-440 RPV Steels - 01 January 2000

STP12409S: Embrittlement, Hardening, and Grain Boundary Composition in an Fe-P-C Alloy after Irradiation or Thermal Aging - 01 January 2000

STP12410S: Microstructure and Hardening in Thermally Aged and Neutron-Irradiated Fe-Cu Model Alloy - 01 January 2000

STP12411S: Neutron Irradiation Rate Dependence of Damage Structures in Fe-Cu Model Alloys - 01 January 2000

STP12412S: Gamma-Radiation Annealing to Mitigate Neutron-Induced Degradation of Both Model and Structural Reactor Materials - 01 January 2000

STP12413S: Analysis of Stress-Induced Burgers Vector Anisotropy in Pressurized Tube Specimens of Irradiated Ferritic-Martensitic Steels: JFMS and JLF-1 - 01 January 2000

STP12414S: An Evaluation of Neutron Energy Spectrum Effects in Iron Based on Molecular Dynamics Displacement Cascade Simulations - 01 January 2000

STP12415S: Effects of Neutron Irradiation on Fe-Cu Model Alloys and RPV Steels Probed by Positron Annihilation and Hardness Measurements - 01 January 2000

STP12381S: Comparison of Static and Dynamic Transition Temperature Shifts in VVR Reactor Pressure Vessel Steels - 01 January 2000

STP12416S: Irradiation Behavior of Ferritic-Martensitic 9–12%Cr Steels - 01 January 2000

STP12417S: Mechanical Properties and Microstructure of HFR-Irradiated Ferritic/Martensitic Low-Activation Alloys - 01 January 2000

STP12418S: Mechanical Properties of Four 7–9%Cr Reduced Activation Martensitic Steels after 2.5 dpa, 300°C Irradiation - 01 January 2000

STP12419S: Evaluation of Ductile-Brittle Transition Behavior of Helium-implanted Reduced Activation 9Cr-2W Martensitic Steel by Small Punch Tests - 01 January 2000

STP12420S: Irradiation Creep of Austenitic Steels Irradiated Up to High Damage Dose - 01 January 2000

STP12421S: Reanalysis of Swelling and Irradiation Creep Data on 316 Type Stainless Steels Irradiated in the FFTF and Phénix Fast Reactors - 01 January 2000

STP12422S: The Relationship Between Swelling and Irradiation Creep in 20% Cold-Worked 316 Stainless Steel - 01 January 2000

STP12423S: Irradiation Creep and Stress-Affected Swelling in Austenitic Stainless Steel 16Cr-15Ni-3Mo-Nb-B Irradiated in the BN-350 Reactor - 01 January 2000

STP12424S: Effects of Impurity on Radiation Creep Rate of the Interstitial Solid Solutions - 01 January 2000

STP12425S: On the Role of Internal Stresses in Void Denuded Zone Formation Under HVEM-Irradiation of Metals and Alloys Preconditioned by Reactor Exposure - 01 January 2000

STP12382S: Effect of Radiation on Material Used for 600MW Chinese Nuclear Power Plant Reactor Pressure Vessel - 01 January 2000

STP12426S: Creep-Fatigue Response of 20% CW 316 SS Under Irradiation at 60°C - 01 January 2000

STP12427S: In-Reactor Creep Regularities of Copper - 01 January 2000

STP12428S: The Correlation Between Swelling and Radiation-Induced Segregation in Iron-Chromium-Nickel Alloys - 01 January 2000

STP12429S: Effect of IVa and Va Elements on Void Formation in Neutron-Irradiated 316 Stainless Steels - 01 January 2000

STP12430S: The Question of Saturation of Void Swelling in Fe-Cr-Ni Austenitic Alloys - 01 January 2000

STP12383S: Comparison of Fracture Toughness of Irradiated Reactor Vessel Welds — Predicted by ASTM E 900 and Measured - 01 January 2000

STP12431S: Influence of Minor Alloying Elements and Stress on Microstructural Evolution and Void Swelling of Austenitic Steels Under Neutron Irradiation - 01 January 2000

STP12432S: Temperature-Shift of Void Swelling Observed in Annealed Fe-18Cr-10Ni-Ti Stainless Steel Irradiated in the Reflector Region of BOR-60 - 01 January 2000

STP12433S: The Effect of Molybdenum on the Grain Boundary Segregation of Chromium Exhibited by Austenitic Stainless Steels after Neutron Irradiation in a BWR - 01 January 2000

STP12434S: Microstructure Modeling of a 316L Stainless Steel Irradiated with Electrons - 01 January 2000

STP12435S: Effects of Damage Rate on Formation of Voids and Dislocation Loops in Metals - 01 January 2000

STP12436S: Stress-Affected Dislocation Development of Stainless Steel During Neutron Irradiation - 01 January 2000

STP12437S: Influence of Silicon or Titanium on the Microstructural Evolution of Fe-Cr-35Ni Alloys Irradiated with Neutrons or Self-Ions - 01 January 2000

STP12438S: Void-Induced Swelling and Embrittlement in the Russian EI-847 Stainless Steel at PWR-Relevant End-of-Life Conditions - 01 January 2000

STP12384S: Neutron Spectrum Effect and Damage Analysis on Pressure Vessel Steel Irradiation Behaviour - 01 January 2000

STP12439S: Interaction of Void-Induced Phase Instability and Subsequent Void Growth in AISI 304 Stainless Steel - 01 January 2000

STP12440S: On the Formation of α-Ferrite in Stainless Steel Alloys - 01 January 2000

STP12441S: A Composite Model for Segregation and Microstructural Evolution Under Electron Irradiation - 01 January 2000

STP12442S: Stress-Modified Welding of Neutron Irradiated Steels - 01 January 2000

STP12443S: Thick Plate Welding of Irradiated Stainless Steel - 01 January 2000

STP12444S: Cracks in TIG Welded, Neutron-Irradiated 304 Stainless Steel - 01 January 2000

STP12445S: Modeling of Helium Bubble Formation During Welding of Irradiated Stainless Steels - 01 January 2000

STP12446S: Effect of Neutron Irradiation on Mechanical Properties of Cn-Alloy/SS316 Joints - 01 January 2000

STP12385S: Characterization of the Decommissioned Novovoronesh-1 Pressure Vessel Wall Materials by Through-Wall Trepans - 01 January 2000

STP15257S: Thermo-mechanical Out-of-Phase Fatigue Life of Overlay Coated IN-738LC Gas Turbine Material - 01 January 2000

STP15267S: New Testing Facility and Concept for Life Prediction of TBC Turbine Engine Components - 01 January 2000

STP13460S: Standardized Testing Procedures and Developments in Partial Discharge Measurement - 01 January 2000

STP13461S: Long-Term Endurance Determinations Using Traditional Accelerated Aging in Combination with Oxidative Stability Testing Resorting to Isothermal DSC Measurements of Oxidation Induction and Maximum Times - 01 January 2000

STP13450S: Current Structure and Activities of ASTM Committee D09 - 01 January 2000

STP13462S: Comparative Tracking Index of Flame-Retardant Nylon and PBT - 01 January 2000

STP13463S: Modern, Low Fire Hazard, Thin Wall Insulated Wire—A Complex Balance of Properties - 01 January 2000

STP13464S: Fire Testing of Electrical Materials - 01 January 2000

STP13451S: Structures and Activities of ASTM Committee D-27 - 01 January 2000

STP13452S: Fire Hazard Testing in the International Electrotechnical Commission Standards: An Overview of IEC TC 89 Activities - 01 January 2000

STP13453S: NEMA Activities and Their Relation to ASTM Committee D09 - 01 January 2000

STP13454S: Specification Issues Associated with the Development of an Agriculturally Based Biodegradable Dielectric Fluid - 01 January 2000

STP13449S: ASTM Committee D09—A History of Success - 01 January 2000

STP13455S: The Big Question: When Should One Recommend Taking a Transformer Out of Service? - 01 January 2000

STP13456S: Sources of Systematic Bias Reflected in an ASTM Collaborative Study on Water in Oil Measured by the Karl Fischer Method - 01 January 2000

STP13457S: The Electrochemical Stability of Mineral Insulating Oils - 01 January 2000

STP13458S: Electrical Insulating Mineral Oils: Specifications and Products - 01 January 2000

STP13459S: New Ways of Disruptive Discharge Recognition in Insulation Testing Devices - 01 January 2000

STP10218S: Deterministic Prediction of Localized Corrosion Damage in Power Plant Coolant Circuits - 01 January 2000

STP10220S: An Analysis of Baffle/Former Bolt Cracking in French PWRs - 01 January 2000

STP10221S: Improvement of IASCC Resistance for Austenitic Stainless Steels in PWR Environment - 01 January 2000

STP10222S: Prediction of Conditions Leading to Stress Corrosion Cracking of Gas Transmission Lines - 01 January 2000

STP13918S: The Effects of Irradiation on the Mechanical Properties of 6061-T651 Aluminum Base Metal and Weldments - 01 January 1999

STP1325-EB: Effects of Radiation on Materials: 18th International Symposium - 01 January 1999

STP13860S: Small Angle Neutron Scattering Study of Linde 80 RPV Welds - 01 January 1999

STP13919S: Irradiation Induced Growth and Microstructure Evolution of Zr-1.2Sn-1Nb-0.4Fe Under Neutron Irradiation to High Doses - 01 January 1999

STP13920S: The Neutron Irradiation Effect on the Mechanical Properties and Structure of Beryllium - 01 January 1999

STP13921S: In-Situ Radio-Luminescence from Sapphires Under Fission Reactor Irradiation - 01 January 1999

STP13922S: The Effects of Constraint, Loading Rate and Irradiation on the Toughness-Temperature Behavior of a V-4Cr-4Ti Alloy - 01 January 1999

STP13923S: Effects of Helium on Void Swelling Behavior of Vanadium Alloys Using Dual Ion Beam Irradiation - 01 January 1999

STP13924S: Effects of Low Temperature Irradiation on the Mechanical Properties of V-4Cr-4Ti - 01 January 1999

STP13861S: Evaluation of Variability in Material Properties and Chemical Composition for Midland Reactor Weld WF-70 - 01 January 1999

STP13855S: The Impact of Mobile Point Defect Clusters in a Kinetic Model of Pressure Vessel Embrittlement - 01 January 1999

STP13862S: Fracture Toughness Testing of Linde 1092 Reactor Vessel Welds in the Transition Range Using Charpy-Sized Specimens - 01 January 1999

STP13863S: Comparison of Irradiation-Induced Shifts of KJc and Charpy Impact Toughness for Reactor Pressure Vessel Steels - 01 January 1999

STP13864S: Miniaturized Charpy Test for Reactor Pressure Vessel Embrittlement Characterization - 01 January 1999

STP13865S: Use of Forces from Instrumented Charpy V-Notch Testing to Determine Crack-Arrest Toughness - 01 January 1999

STP13866S: The Ductile-Brittle Transition Behaviour of Submerged-Arc Weldments Following High Temperature Exposure - 01 January 1999

STP13867S: Irradiation of Vessel Materials Using KORPUS Facility of RBT-6 Reactor - 01 January 1999

STP13868S: Auger Spectroscopy of Magnox Pressure Vessel Steels - 01 January 1999

STP13869S: Phosphorus Free Energy Change Associated with Segregation to Grain Boundaries in Submerged-Arc Welds - 01 January 1999

STP13870S: Irradiation Embrittlement of Reactor Pressure Vessel Steels due to Mechanisms Other than Radiation Hardening - 01 January 1999

STP13871S: Temper Embrittlement, Irradiation Induced Phosphorus Segregation and Implications for Post-Irradiation Annealing of Reactor Pressure Vessels - 01 January 1999

STP13856S: An Analysis of Radiation Effects in Model A533B Pressure Vessel Steels Containing Copper, Phosphorus and Nickel Additions - 01 January 1999

STP13872S: The Effect of Heat Treatment on Phosphorus Segregation in a Submerged-Arc Weld Metal - 01 January 1999

STP13873S: SANS Study of High-Copper RPV Welds in Irradiated and Annealed Conditions - 01 January 1999

STP13874S: Investigation of the Development of Irradiation - Induced Precipitates in VVER-440-Type Reactor Pressure Vessel Steels and Weld Metals after Irradiation and Annealing - 01 January 1999

STP13875S: Hardness and Microstructural Response to Thermal Annealing of Irradiated ASTM A533B Class 1 Plate Steel - 01 January 1999

STP13876S: Effects of Damage Rate on Irradiation Hardening and Post-irradiation Annealing Characteristics of Carbon Steel - 01 January 1999

STP13877S: Experimental Tests of Irradiation-Anneal-Reirradiation Effects on Mechanical Properties of RPV Plate and Weld Materials - 01 January 1999

STP13854S: Irradiation Hardening of Pressure Vessel Steels at 60°C: The Role of Thermal Neutrons and Boron - 01 January 1999

STP13878S: Comparison of Different Experimental and Analytical Measures of the Thermal Annealing Response of Neutron-Irradiated RPV Steels - 01 January 1999

STP13879S: The Annealing Recovery of The Palisades Nuclear Power Plant Surveillance Material Using Weld Reconstitution - 01 January 1999

STP13880S: Design of an Annealing Supplemental Surveillance Program for the Palisades Reactor Pressure Vessel - 01 January 1999

STP13881S: Comparison of BR3 Surveillance and Vessel Plates to the Surrogate Plates Representative of the Yankee Rowe PWR Vessel - 01 January 1999

STP13882S: Role and Experience with Thermal Monitors in Reactor Vessel Surveillance Capsules - 01 January 1999

STP13883S: A Consideration of Scatter in Radiation Damage Trend Curves for Reactor Pressure Vessel Steel Plate Materials - 01 January 1999

STP13884S: Refinements to Pressure Vessel Steel Embrittlement Correlations - 01 January 1999

STP13885S: Development of Embrittlement Prediction Models for U.S. Power Reactors and The Impact of The Heat-Affected Zone to Thermal Annealing - 01 January 1999

STP13857S: An Assessment of Potential Gamma Ray Enhancement of Embrittlement in ABWR Pressure Vessel Walls - 01 January 1999

STP13886S: Empirical Correlation of Observed Three Stages of Fast Neutron Irradiation Hardening and Embrittlement in WWER-440 Pressure Vessel Materials - 01 January 1999

STP13887S: Evaluation of Irradiated Pressure Vessel Steel by Mechanical Tests and Positron Annihilation Lineshape Analysis - 01 January 1999

STP13888S: Detection of Radiation Damage in Low Alloy Steel Using a Squid Sensor - 01 January 1999

STP13889S: Nondestructive Evaluation of Neutron Irradiation Embrittlement for Reactor Vessel Steel by Magnetomechanical Acoustic Emission Technique - 01 January 1999

STP13890S: Changes in Electromagnetic Properties of a Low-Alloy Steel Caused by Neutron Irradiation - 01 January 1999

STP13891S: Detection of Irradiation Embrittlement of Low-Alloy Steel for Nuclear Reactor Pressure Vessels Using a Probe Type Eddy Current Sensor - 01 January 1999

STP13892S: The Effect of Ordering on Radiation-Induced Segregation in Austenitic Iron- and Nickel-Base Alloys - 01 January 1999

STP13893S: The Modelling of Combined Radiation-Induced and Thermal Non-Equilibrium Segregation of Chromium in Neutron-Irradiated Austenitic Stainless Steels - 01 January 1999

STP13894S: Radiation-Induced Instability of MnS Precipitates and its Possible Consequences on Irradiation-Induced Stress Corrosion Cracking of Austenitic Stainless Steels - 01 January 1999

STP13895S: Tensile Properties of a Titanium Modified Austenitic Stainless Steel and the Held Joints after Neutron Irradiation - 01 January 1999

STP13896S: Temperature Dependence of the Deformation Behavior of Type 316 Stainless Steel after Low Temperature Neutron Irradiation - 01 January 1999

STP13897S: Microstructures in Neutron Irradiated Fe-Cr-Ni-P-Ti Model Austenitic Alloys Doped with 10B - 01 January 1999

STP13898S: Behavior of Fe-Cr-Ni-xP-yTi Alloys under Electron/He Ion Dual Beam Irradiation - 01 January 1999

STP13899S: Comparison of Irradiation Creep and Swelling of an Austenitic Alloy Irradiated in FFTF and PFR - 01 January 1999

STP13900S: Irradiation Creep at Temperatures of 400°C and Below for Application to Near-Term Fusion Devices - 01 January 1999

STP13901S: Irradiation Creep in Nickel Containing and in Manganese Containing Stainless Steel Alloys - 01 January 1999

STP13858S: Dynamic Finite Element Modeling of the Upper Shelf Energy of Precracked Charpy Specimens of Neutron Irradiated Weld Metal 72W - 01 January 1999

STP13902S: Variability of Irradiation Creep and Swelling of HT9 Irradiated to High Neutron Fluence at 400–600°C - 01 January 1999

STP13903S: Evaluation of Low-Temperature Swelling in Austenitic Stainless Steels - 01 January 1999

STP13904S: A Reevaluation of Helium/dpa and Hydrogen/dpa Ratios for Fast Reactor and Thermal Reactor Data Used in Fission-Fusion Correlations - 01 January 1999

STP13905S: The Effects of Phase Stability on Void Swelling in P, Ti-Modified 316 Stainless Steels During Neutron Irradiation - 01 January 1999

STP13906S: The Dependence of Swelling on Phosphorus Content in Stainless Steels Containing High Silicon Levels - 01 January 1999

STP13907S: Neutron Irradiation Creep at 100°C on 316L, AMCR, and Welded 316L Stainless Steel Alloys - 01 January 1999

STP13908S: Effect of Radiation-Induced Segregation on Precipitate Stability and Swelling in Irradiated Alloys - 01 January 1999

STP13909S: Microstructural and Microchemical Characterisation of Ferritic Ex-Service Magnox Control Rod Sheath Material - 01 January 1999

STP13910S: Behavior of an Oxide Dispersion Strengthened Ferritic Steel Irradiated in Phenix - 01 January 1999

STP13859S: Anomalous Hardening in Model Alloys and Steels Thermally Aged at 290°C and 350°C: Implications to Low Flux Irradiation Embrittlement - 01 January 1999

STP13911S: The Consequences of Helium Production and Nickel Additions on Microstructural Development in Isotopically Tailored Ferritic Alloys - 01 January 1999

STP13912S: Tensile and Charpy Impact Properties of Irradiated Reduced Activation Ferritic Steels - 01 January 1999

STP13913S: Impact Behavior of Low Activation Steels at 30 dpa - 01 January 1999

STP13914S: Electron Microscopy of Precipitation and Age Hardening in Fe-0.6Cu Model Alloy - 01 January 1999

STP13915S: Brazed Dispersion Strengthened Copper: The Effect of Neutron Irradiation and Transmutation on Bond Integrity - 01 January 1999

STP13916S: Void Swelling of Copper and Copper Alloys Induced by Heavy Ion Irradiation - 01 January 1999

STP13917S: Radiation-Enhanced Diffusion of 63Ni in Nickel and in Copper - 01 January 1999

STP14941S: Dynamic Initiation Fracture Toughness of a Pressure Vessel Steel in the Transition Region - 01 January 1999

STP14955S: The Use of Local Approach to Fracture in Reactor Pressure Vessel Structural Integrity Assessment: Synthesis of a Cooperative Research Program Between EDF, CEA, Framatome and AEA Technology - 01 January 1999

STP14957S: Micromechanical Prediction of Fracture Toughness for Pressure Vessel Steel Using a Coupled Model - 01 January 1999

STP14987S: Fracture Analysis of Ductile Crack Growth in Weld Material from a Full-Thickness Clad RPV Shell Segment - 01 January 1999

STP15791S: Field Data on Testing of Natural Gas Vehicle (NGV) Containers Using Proposed ASTM Standard Test Method for Examination of Gas-Filled Filament-Wound Pressure Vessels Using Acoustic Emission (ASTM E070403-95/1) - 01 January 1999

STP37986S: Dependence of Ductile-Brittle Transition Behavior on the Size of Charpy Specimen and The Location Of V-Notch in the Haz of Welded A533B PVS - 01 January 1998

STP1329-EB: Small Specimen Test Techniques - 01 January 1998

STP37987S: Analysis of Procedures for the Determination of the Yield Force (Fgy) for Instrumented Sub-Sized Charpy-V Specimens - 01 January 1998

STP37988S: Fracture Toughness Testing of Small and Standard Bending Specimens - 01 January 1998

STP37989S: The Actual Properties of WWER-440 Reactor Pressure Vessel Materials Obtained by Impact Tests of Subsize Specimens Fabricated out of Samples Taken from the RPV - 01 January 1998

STP37980S: Sub-Size Impact Testing: CISE Experience and the Activity of the ESIS TC5 Sub-Committee - 01 January 1998

STP37990S: Small Specimen Testing Applied at Surveillance Extension - 01 January 1998

STP37991S: Fracture Toughness Test on Precracked Charpy Specimens in The Transition Range for Linde 80 Weld Metals - 01 January 1998

STP37992S: The Applicability of Small and Ultra-Small Fracture Toughness Specimens for Material Characterization - 01 January 1998

STP37993S: Fracture Toughness Measurements in the Transition Regime Using Small Size Samples - 01 January 1998

STP37994S: Use of Precracked Charpy and Smaller Specimens to Establish the Master Curve - 01 January 1998

STP37995S: On the Utilization of High Rate Pre-Cracked Charpy Test Results and the Master Curve to Obtain Accurate Lower Bound Toughness Predictions in the Ductile-to-Brittle Transition - 01 January 1998

STP37996S: Characterization by Notched and Precracked Charpy Tests of the in-Service Degradation of Reactor Pressure Vessel Steel Fracture Toughness - 01 January 1998

STP37997S: Developing Fracture Assessment Methods for Fusion Reactor Materials with Small Specimens - 01 January 1998

STP37998S: Using Small Cracked Round Bars to Measure the Fracture Toughness of a Pressure Vessel Steel Weldment: A Feasibility Study - 01 January 1998

STP37981S: Comparison of Results of Instrumented Charpy- and Mini-Charpy Tests with Different RPV-Steels - 01 January 1998

STP37999S: Estimation of Fracture Toughness Values for Titanium Alloy Using Small Centre Notched Round Specimens - 01 January 1998

STP38000S: Fracture Toughness Derived from Small Circumferentially Cracked Bars - 01 January 1998

STP38001S: Critical Analysis of Results from the ASTM Round-Robin on Reconstitution - 01 January 1998

STP37979S: ASTM Cross-Comparison Exercise on Determination of Material Properties Through Miniature Sample Testing - 01 January 1998

STP38002S: Comparison of Compact, Reconstituted and Subsize Charpy Specimens - 01 January 1998

STP38003S: Specimen Reconstitution Technique and Verification Testing for Charpy Size SENB Specimens - 01 January 1998

STP38004S: The Effects of the Configuration of a Weld-reconstituted Compact Tension Specimen on Fracture Toughness Determination - 01 January 1998

STP38005S: Reconstitution of Sub Charpy-size V-notched and Pre-Cracked Specimens - 01 January 1998

STP38006S: Reconstitution of Fracture Toughness Specimen for Surveillance Test - 01 January 1998

STP38007S: Reconstitution of Charpy Impact Specimens by Surface Activated Joining - 01 January 1998

STP37982S: Fracture Toughness Evaluation From Instrumented Sub-Size Charpy-Type Tests - 01 January 1998

STP38008S: Microspecimen Tensile Tests of A533-B Steel - 01 January 1998

STP38009S: Evaluation of the Fracture Toughness of a C-MN Steel Using Small Notched Tensile Specimens - 01 January 1998

STP38010S: Miniature Shear Punch Test with On-Line Acoustic Emission Monitoring for Assessment of Mechanical Properties - 01 January 1998

STP38011S: The Use of a Small Punch Test Procedure to Determine Mechanical Properties - 01 January 1998

STP38012S: Fracture and Tensile Properties of ASTM Cross-Comparison Exercise A 533B Steel by Small Punch Testing - 01 January 1998

STP38013S: Effect of Specimen Thickness on the Tensile Deformation Properties of SA508 Cl.3 Reactor Pressure Vessel Steel - 01 January 1998

STP38014S: The Prediction of Fracture Toughness Properties from 3MM Diameter Punch Discs - 01 January 1998

STP38015S: Evaluation of Ductility of Zircaloy-2 Materials Using a Small Ellipsoidal-Shaped Punch - 01 January 1998

STP38016S: The use of Shear Punch Testing to Clarify the Consequences of Helium Production in the Deformation of Isotopically Tailored Ferritic Alloys - 01 January 1998

STP37983S: Characterization of Ductile Fracture Toughness Based on Subsized Charpy and Tensile Test Results - 01 January 1998

STP37984S: Effects of Ligament Size and Tensile Properties on the Fracture of Pressure Vessel Materials Under Impact Loading - 01 January 1998

STP37985S: Instrumented Impact Testing of Subsize Charpy V-Notch Specimens - 01 January 1998

STP15718S: Results of the Lifetime Round Robins Done in the Framework of the Semi M6 Solar Silicon Standardization Task Force - 01 January 1998

STP15731S: Determination of Radionuclides in Biological Fluids Using a High Resolution ICP-MS in Low Resolution Mode - 01 January 1998

STP1344-EB: Applications of Inductively Coupled Plasma-Mass Spectrometry to Radionuclide Determinations - 01 January 1998

STP15732S: High-Precision Determination of 234U/238U Activity Ratios in Natural Waters and Carbonates by ICPMS - 01 January 1998

STP15733S: Isotope Ratios of Uranium Using High Resolution Inductively Coupled Plasma—Mass Spectrometry (ICP-MS) - 01 January 1998

STP15722S: A Study of Isotopic Homogeneity in “Blended Uranium” Using ICP-MS - 01 January 1998

STP15723S: High Precisin and High Accuracy Isotopic Measurement of Uranium Using Lead and Thorium Calibration Solutions by Inductively Coupled Plasma-Multiple Collector-Mass Spectrometry - 01 January 1998

STP15724S: Actinide, Elemental, and Fission Product Measurements by ICPMS at the Savannah River Site - 01 January 1998

STP15721S: Uranium Isotope Measurements by Quadrupole ICP-MS for Process Monitoring of Enrichment - 01 January 1998

STP15725S: Evaluation of Nebulizer Performance within the ICP-MS Measurement System for Analysis of SRS Radiological Waste Tank Simulated Solutions - 01 January 1998

STP15726S: Determination of Long-Lived Beta Emitters in Nuclear Waste by Inductively Coupled Plasma-Mass Spectrometry - 01 January 1998

STP15727S: Determination of Technetium-99, Neptunium-237 and Isotopes of Thorium in Uranyl Nitrate Solutions From a Reprocessing Plant, Using Double-Focusing ICP-MS - 01 January 1998

STP15728S: Evaluation of Chelation Preconcentration for the Determination of Actinide Elements by Flow Injection ICP-MS - 01 January 1998

STP15729S: Determination of Uranium in Clinical and Environmental Samples by FIAS-ICPMS - 01 January 1998

STP15730S: 99Tc Bioassay: A Direct Comparison of Liquid Scintillation Radiation Detection and ICP-MS Mass Detection of the 99Tc Isotope - 01 January 1998

STP16590S: Improved Mechanical Properties of the A 508 Class 3 Steel for Nuclear Pressure Vessel Through Steelmaking - 01 January 1997

STP16606S: Martensitic 11% CrMoNiNb Steel for Turbine Rotors in Geothermal Power Stations - 01 January 1997

STP16607S: Development of High Strength 12% Cr Ferritic Steel for Turbine Rotor Operating above 600‡C - 01 January 1997

STP16608S: Historical Overview of Improving Cleanliness of Rotor Steels for Electric Utility Applications - 01 January 1997

STP16609S: Prediction and Control of Segregations in CrMoV Steel Ingot for Monoblock HLP Rotor Forgings Using Experimental Results Obtained from 8 Ton Sand Mold Ingots - 01 January 1997

STP16610S: High Strength 12% Cr Heat Resisting Steel for High Temperature Steam Turbine Blade - 01 January 1997

STP16611S: Manufacturing and Properties of Newly Developed 9%CrMoVNiNbN High-Pressure Low-Pressure Rotor Shaft Forging - 01 January 1997

STP16591S: Effects of Composition and Heat Treatment on the Toughness of ASTM A508 Grade 3 Class 1 Material for Pressure Vessels - 01 January 1997

STP16589S: New Materials and Forgings Used for Pressure Vessels Operating in Hydrogen Environment - 01 January 1997

STP16592S: Current Forgings and their Properties for Steam Generator of Nuclear Plant - 01 January 1997

STP16593S: Forging Technology Adapted to the Manufacture of Nuclear PWR Austenitic Primary Piping - 01 January 1997

STP16594S: The Optimization of Mechanical Properties for Nuclear Transportation Casks in ASTM A350 LF5 - 01 January 1997

STP16246S: The Effect of Cyclic Loading During Ductile Tearing on the Fracture Resistance of Nuclear Pipe Steels - 01 January 1997

STP19959S: A Process Model for the Initiation of Stress-Corrosion Crack Growth in BWR Plant Materials - 01 January 1997

STP19962S: Interactive Effect of Dynamic Strain Ageing with High Temperature Water on the Crack Initiation Behaviour of Reactor Pressure Vessel Steels - 01 January 1997

STP19964S: Effects of Temperature and Dissolved Oxygen Contents on Fatigue Lives of Carbon and Low Alloy Steels in LWR Water Environments - 01 January 1997

STP19965S: Evaluation of Effects of LWR Coolant Environments on Fatigue Life of Carbon and Low-Alloy Steels - 01 January 1997

STP19967S: Advances in Environmental Fatigue Evaluation for Light Water Reactor Components - 01 January 1997

STP19952S: Initiation of Stress-Corrosion Cracking on Gas Transmission Piping - 01 January 1997

STP11355S: Monitoring Biofilm Formation in Power Plant Environments - 01 January 1997

STP11849S: Evaluation of the Lubrication Properties of Biodegradable Fluids and Their Potential to Replace Mineral Oil in Heavily Loaded Hydrostatic Transmissions - 01 January 1997

STP11850S: Testing Method for Biodegradable Hydraulic Pressure Media Based on Natural and Synthetic Esters - 01 January 1997

STP13778S: Development of Comprehensive Material Performance Database for Nuclear Applications - 01 January 1997

STP11900S: Using Ultrasonic Measurements and a Two-Phase Composite Model to Assess Radiation Damage in Reactor Pressure Vessel Steels - 01 January 1997

STP12309S: Estimation of Lower-Bound KJc on Pressure Vessel Steels from Invalid Data - 01 January 1997

STP12312S: Application of Small Specimens to Fracture Mechanics Characterization of Irradiated Pressure Vessel Steels - 01 January 1997

STP12326S: Fracture Assessment of Weld Material From a Full-Thickness Clad RPV Shell Segment - 01 January 1997

STP12328S: Analysis of Unclad and Sub-Clad Semi-Elliptical Flaws in Pressure Vessel Steels - 01 January 1997

STP12329S: Predicting Crack Instability Behaviour of Burst Tests from Small Specimens for Irradiated Zr-2.5Nb Pressure Tubes - 01 January 1997

STP14078S: Evaluating the Comfort Performance of Fabrics for Nuclear Protective Apparel - 01 January 1996

STP16446S: Effects of Cycle Type and Coating on the TMF Lives of a Single Crystal Nickel Based Gas Turbine Blade Alloy - 01 January 1996

STP16522S: Bubble Microstructure Evolution and Helium Behavior in He+ Implanted Ni-Base Alloys - 01 January 1996

STP1270-EB: Effects of Radiation on Materials: 17th International Symposium - 01 January 1996

STP16523S: Saturation of Swelling in Neutron Irradiated Pure Nickel and Its Dependence on Temperature and Starting Dislocation Microstructure - 01 January 1996

STP16470S: The Modelling of Irradiation Embrittlement in Submerged-Arc Welds - 01 January 1996

STP16524S: Effect of Irradiation in a Spallation Neutron Environment on Tensile Properties and Microstructure of Aluminum Alloys 5052 and 6061 - 01 January 1996

STP16525S: Correlation Between Shear Punch and Tensile Data for Neutron-Irradiated Aluminum Alloys - 01 January 1996

STP16526S: Effect of Dynamically Charged Helium on Mechanical Properties of Vanadium-Base Alloys - 01 January 1996

STP16527S: Swelling and Structure of Vanadium-Base Alloys Irradiated in the Dynamic Helium Charging Experiment - 01 January 1996

STP16528S: Corrosion Response of Pre-Irradiated Zr-2.5Nb Pressure Tube Material - 01 January 1996

STP16529S: The Development of Structural Materials for Reduced Long-Term Activation - 01 January 1996

STP16530S: Characterization of Irradiation-Induced Precipitates by Small Angle X-Ray and Neutron Scattering Experiments - 01 January 1996

STP16531S: Variable Energy Positron Measurements at Nitrogen Ion Bombarded Steel Surfaces - 01 January 1996

STP16532S: Use of Laser Extensometer for Mechanical Tests on Irradiated Materials - 01 January 1996

STP16471S: The Modelling of Irradiation-Enhanced Phosphorus Segregation in Neutron Irradiated Reactor Pressure Vessel Submerged-Arc Welds - 01 January 1996

STP16472S: Research to Understand the Embrittlement Behavior of Yankee/BR3 Surveillance Plate and Other Outlier RPV Steels - 01 January 1996

STP16473S: Electron Microscopy and Small Angle Neutron Scattering Study of Precipitation in Low Alloy Steel Submerged-Arc Welds - 01 January 1996

STP16474S: Radiation Damage Studies Using Small-Angle Neutron Scattering - 01 January 1996

STP16475S: Damage Structures of Proton Irradiated Fe-0.3wt.%Cu Alloy - 01 January 1996

STP16476S: Mitigation of Irradiation Embrittlement by Annealing - 01 January 1996

STP16477S: Microstructure and Mechanical Properties of WWER-440 Reactor Vessel Metal After Service Life Expiration and Recovery Anneal - 01 January 1996

STP16466S: Pressure Vessel Embrittlement Predictions Based on a Composite Model of Copper Precipitation and Point Defect Clustering - 01 January 1996

STP16478S: A Microstructural Study of Phosphorus Segregation and Intergranular Fracture in Neutron Irradiated Submerged-Arc Welds - 01 January 1996

STP16479S: Effects of Annealing Time on the Recovery of Charpy V-Notch Properties of Irradiated High-Ccopper Weld Metal - 01 January 1996

STP16480S: In-Service Embrittlement of the Pressure Vessel Welds at the Doel I And II Nuclear Power Plants - 01 January 1996

STP16481S: The Toughness of Irradiated Pressure Water Reactor (PWR) Vessel Shell Rings and the Effect of Segregation Zones - 01 January 1996

STP16482S: Low Temperature Embrittlement of RPV Support Structure Steel - 01 January 1996

STP16483S: Effects of Neutron Flux and Irradiation Temperature on Irradiation Embrittlement of A533B Steels - 01 January 1996

STP16484S: The Interpretation of Charpy Impact Test Data Using Hyper-Logistic Fitting Functions - 01 January 1996

STP16485S: Uncertainty Evaluation in Transition Temperature Measurements - 01 January 1996

STP16486S: On Impact Testing of Subsize Charpy V-Notch Type Specimens - 01 January 1996

STP16465S: Mechanisms Controlling the Composition Influence on Radiation Hardening and Embrittlement of Iron-Base Alloys - 01 January 1996

STP16487S: Reconstitution: Where Do We Stand? - 01 January 1996

STP16488S: The Reconstitution of Charpy-Size Tensile Specimens - 01 January 1996

STP16489S: Notch Reorientation of Charpy-V Specimens of the BWR Philippsburg 1 Through Reconstitution - 01 January 1996

STP16490S: Variations in Charpy Impact Data Evaluated by a Round-Robin Testing Program — A Summary - 01 January 1996

STP16491S: The Embrittlement Data Base (EDB) and Its Applications - 01 January 1996

STP16492S: Surveillance Programme for WWER-440/Type 213 Reactor Pressure Vessels- Standard Programme, Re-Evaluation of Results, Supplementary Programme - 01 January 1996

STP16493S: Application of Micromechanical Models of Ductile Fracture Initiation to Reactor Pressure Vessel Materials - 01 January 1996

STP16494S: On the Effect of Flux and Composition on Irradiation Hardening at 60°C - 01 January 1996

STP16495S: The Dependence of Radiation Hardening and Embrittlement on Irradiation Temperature - 01 January 1996

STP16496S: HFIR Steels Embrittlement: The Possible Effect of Gamma Field Contribution - 01 January 1996

STP16467S: The B&W Owners Group Program for Microstructural Characterization and Radiation Embrittlement Modelling of Linde 80 Reactor Vessel Welds - 01 January 1996

STP16497S: The Influence of Metallurgical Variables on the Temperature Dependence of Irradiation Hardening in Pressure Vessel Steels - 01 January 1996

STP16498S: Effects of Proton Irradiation on Positron Annihilation and Micro-Vickers Hardness of Fe-C-Cu Model Alloys - 01 January 1996

STP16499S: Ductile Fracture Mechanisms in an A302B Modified Reactor Pressure Vessel Steel - 01 January 1996

STP16500S: Fracture Toughness Test Results of Thermal Aged Reactor Vessel Materials - 01 January 1996

STP16501S: The Effect of Constraint on Toughness of a Pressure Vessel Steel - 01 January 1996

STP16468S: Irradiation Embrittlement Modelling of Linde 80 Weld Metals - 01 January 1996

STP16502S: The Effects of Thermal Annealing on Fracture Toughness of Low Upper-Shelf Welds - 01 January 1996

STP16503S: Evaluation of Embrittlement in a Pressure Vessel Steel by Fracture Reconstruction - 01 January 1996

STP16504S: The Microstructural Stability and Mechanical Properties of Two Low Activation Martensitic Steels - 01 January 1996

STP16505S: Influence of Thermomechanical Treatment on Irradiation Microstructures in an ODS Ferritic Steel - 01 January 1996

STP16506S: Effect of Boron on Post Irradiation Tensile Properties of Reduced Activation Ferritic Steel (F-82H) Irradiated in HFIR - 01 January 1996

STP16507S: Irradiation Effects on Base Metal and Welds of 9Cr-1Mo (EM10) Martensitic Steel - 01 January 1996

STP16508S: Evaluation of the Upper Shelf Energy for Ferritic Steels from Miniaturized Charpy Specimen Data - 01 January 1996

STP16509S: On the Role of Strain Rate, Size and Notch Acuity on Toughness: A Comparison of Two Martensitic Stainless Steels - 01 January 1996

STP16510S: Microstructural Evolution of Austenitic Stainless Steels Irradiated in a Fast Reactor - 01 January 1996

STP16511S: Effects of Helium/DPA Ratio, Alloy Composition and Cold Work on Microstructural Evolution and Hardening of 59Ni-Doped Fe-Cr-Ni Alloys Neutron-Irradiated at 465°C - 01 January 1996

STP16512S: Swelling, Mechanical Properties and Structure of Austenitic High-Nickel Alloy Irradiated in a Fast Reactor - 01 January 1996

STP16513S: Effects of Metallurgical Variables on Swelling of Modified 316 and Higher Ni Austenitic Stainless Steels - 01 January 1996

STP16469S: Modeling of Irradiation Embrittlement and Annealing/Recovery in Pressure Vessel Steels - 01 January 1996

STP16514S: On the Fundamentals of Radiation Damage in FCC Materials, A Review - 01 January 1996

STP16515S: An Investigation of Microstructures and Yield Strengths in Irradiated Austenitic Stainless Steels Using Small Specimen Techniques - 01 January 1996

STP16516S: Irradiation Hardening and Loss of Ductility of Type 316L(N) Stainless Steel Plate Material Due to Neutron-Irradiation - 01 January 1996

STP16517S: Fatigue Crack Propagation by Channel Fracture in Irradiated 316 Stainless Steel - 01 January 1996

STP16518S: Fracture Toughness of Irradiated Candidate Materials for ITER First Wall/Blanket Structures - 01 January 1996

STP16519S: Irradiation Behavior of Weldments of Austenitic Stainless Steel Made by Various Welding Techniques - 01 January 1996

STP16520S: Helium Effects on the Reweldability and Low Cycle Fatigue Properties of Welded Joints for Type Cr16Ni11Mo3Ti and 316L(N) Stainless Steels - 01 January 1996

STP16521S: Data Collection on the Effect of Irradiation on the Mechanical Properties of Austenitic Stainless Steels and Weld Metals - 01 January 1996

STP37961S: The Use of Electrochemical Noise Measurements with Nuclear Waste Tanks - 01 January 1996

STP37963S: Simultaneous Corrosion and Fouling Monitoring Under Heat Transfer in Cooling Water Systems - 01 January 1996

STP37965S: The Use of Electrochemical Noise to Investigate the Corrosion Resistance of UNS Alloy N04400 Nuclear Heat Exchanger Tubes - 01 January 1996

STP37966S: The Use of Electrochemical Noise Measurement in the Evaluation of Materials for Steam Generators - 01 January 1996

STP16156S: Durability Studies of Solar Reflector Materials Exposed to Environmental Stresses - 01 January 1996

STP16159S: Development of a Methodology for Service Lifetime Prediction of Renewable Energy Devices - 01 January 1996

STP16161S: Performance Degradation, Polymer Encapsulant Degradation, and Estimating Lifetimes for Photovoltaic Modules from Accelerated Testing - 01 January 1996

STP16170S: Mechanisms of LiOH Degradation and H3BO3Repair of ZrO2 Films - 01 January 1996

STP1295-EB: Zirconium in the Nuclear Industry: Eleventh International Symposium - 01 January 1996

STP16165S: Behavior and Properties of Zircaloys in Power Reactors: A Short Review of Pertinent Aspects in LWR Fuel - 01 January 1996

STP16171S: PWR Zircaloy Fuel Cladding Corrosion Performance, Mechanisms, and Modeling - 01 January 1996

STP16172S: Correlation Between Electrochemical Properties and Corrosion Resistance of Zirconium Alloys - 01 January 1996

STP16173S: Long-Term In Situ Corrosion Investigation of Zr Alloys in Simulated PWR Environment by Electrochemical Measurements - 01 January 1996

STP16174S: Anodic Protection Provided by Precipitates in Aqueous Corrosion of Zircaloy - 01 January 1996

STP16175S: Investigation of In-Pile Grown Corrosion Films on Zirconium-Based Alloys - 01 January 1996

STP16176S: Microstructure Evolutions and Iron Redistribution in Zircaloy Oxide Layers: Comparative Effects of Neutron Irradiation Flux and Irradiation Damages - 01 January 1996

STP16177S: Oxide Characteristics and Corrosion and Hydrogen Uptake in Zr-2.5 Nb CANDU Pressure Tubes - 01 January 1996

STP16178S: The Effect of the Trace Impurity Uranium on PWR Aqueous Corrosion of Zircaloy-4 - 01 January 1996

STP16179S: Detrimental Role of Hydrogen on the Corrosion Rate of Zirconium Alloys - 01 January 1996

STP16180S: Hydrogen Pickup and Redistribution in Alpha-Annealed Zircaloy-4 - 01 January 1996

STP16166S: Microstructure of Oxides on Zircaloy-4, 1.0Nb Zircaloy-4, and Zircaloy-2 Formed in 10.3-MPa Steam at 673 K - 01 January 1996

STP16181S: A Unified Model to Describe the Anisotropic Viscoplastic Behavior of Zircaloy-4 Cladding Tubes - 01 January 1996

STP16182S: The Influence of Temperature and Yield Strength on Delayed Hydride Cracking in Hydrided Zircaloy-2 - 01 January 1996

STP16164S: Learning from History: A Case Study in Nuclear Fuel - 01 January 1996

STP16183S: Effects of Hydride Precipitate Localization and Neutron Fluence on the Ductility of Irradiated Zircaloy-4 - 01 January 1996

STP16184S: Fracture Toughness of Zircaloy Cladding Tubes - 01 January 1996

STP16185S: A Model for Analysis of the Effect of Final Annealing on the In- and Out-of-Reactor Creep Behavior of Zircaloy Cladding - 01 January 1996

STP16186S: Properties of an Irradiated Heat-Treated Zr-2.5Nb Pressure Tube Removed From the NPD Reactor - 01 January 1996

STP16187S: Link Between Results of Small- and Large-Scale Toughness Tests on Irradiated Zr-2.5Nb Pressure Tube Material - 01 January 1996

STP16188S: Modeling In-Reactor Deformation of Zr-2.5Nb Pressure Tubes in CANDU Power Reactors - 01 January 1996

STP16189S: Effect of In-PWR Irradiation on Size, Structure, and Composition of Intermetallic Precipitates of Zr Alloys - 01 January 1996

STP16190S: In Situ Studies of Phase Transformations in Zirconium Alloys and Compounds Under Irradiation - 01 January 1996

STP16167S: The Importance of Oxide Morphology for the Oxidation Rate of Zirconium Alloys - 01 January 1996

STP16191S: Evolution of Microstructure in Zirconium Alloys During Irradiation - 01 January 1996

STP16192S: Influence of Neutron Irradiation on Dislocation Structure and Phase Composition of Zr-Base Alloys - 01 January 1996

STP16193S: Non-Linear Irradiation Growth of Cold-Worked Zircaloy-2 - 01 January 1996

STP16194S: Influence of Iron in the Nucleation of ⟨c⟩ Component Dislocation Loops in Irradiated Zircaloy-4 - 01 January 1996

STP16195S: Effects of Extrusion-Billet Preheating on the Microstructure and Properties of Zr-2.5Nb Pressure Tube Materials - 01 January 1996

STP16196S: Zircaloy-2 Lined Zirconium Barrier Fuel Cladding - 01 January 1996

STP16197S: Effects of Microstructure on Ductility and Fracture Resistance of Zr-1.2Sn-1 Nb-0.4Fe Alloy - 01 January 1996

STP16198S: Influence of Processing Variables and Alloy Chemistry on the Corrosion Behavior of ZIRLO Nuclear Fuel Cladding - 01 January 1996

STP16199S: Effects of Thermomechanical Processing on In-Reactor Corrosion and Post-Irradiation Mechanical Properties of Zircaloy-2 - 01 January 1996

STP16168S: Effect of Annealing Temperature on Corrosion Behavior and ZrO2 Microstructure of Zircaloy-4 Cladding Tube - 01 January 1996

STP16200S: Embrittlement of Reactor Core Materials - 01 January 1996

STP16201S: Zirconium Alloy E635 as a Material for Fuel Rod Cladding and Other Components of VVER and RBMK Cores - 01 January 1996

STP16202S: Corrosion Behavior of Duplex and Reference Cladding in NPP Grohnde - 01 January 1996

STP16203S: Development of New Zirconium Alloys for a BWR - 01 January 1996

STP16204S: Comparison of the Long-Time Corrosion Behavior of Certain Zr Alloys in PWR, BWR, and Laboratory Tests - 01 January 1996

STP16205S: In-BWR and Out-of-Pile Nodular Corrosion behavior of Zry-2/4 Type Melts with Varying Fe, Cr, and Ni Content and Varying Process History - 01 January 1996

STP16206S: Development of Pressure Tubes with Service Life Greater Than 30 Years - 01 January 1996

STP16169S: Microstructure of Oxide Films Formed during the Waterside Corrosion of the Zircaloy-4 Cladding in Lithiated Environment - 01 January 1996

STP14624S: Pressure Vessel Fracture Simulation - 01 January 1995

STP13751S: A Semantic Analysis of Russian Terms and Descriptors for Civilian Nuclear Power Plant Fluid System Valves - 01 January 1995

STP13044S: Establishment of Fatigue Test Method for Turbine Blade Fastener - 01 January 1995

STP13046S: The Regulatory Approach to Fastener Integrity in the Nuclear Industry - 01 January 1995

STP14641S: The Effect of Constraint Due to Out-of-Plane Stress Field on Fracture of Reactor Pressure Vessel Steel--An Experimental and Numerical Study - 01 January 1995

STP14644S: Constraint Effects in Testing Different Curved Geometries of Zr-2.5Nb Pressure Tube Material - 01 January 1995

STP14697S: Impact of Air Infiltration in Frame Walls on Energy Loads: Taking Advantage of the Interaction between Infiltration, Solar Radiation, and Conduction - 01 January 1995

STP16399S: Stress-Intensity-Factor Influence Coefficients for Semielliptical Inner-Surface Flaws in Clad Pressure Vessels - 01 January 1995

STP15984S: Determination of Total and Isotopic Uranium and Total Thorium in Soils by Inductively Coupled Plasma-Mass Spectrometry - 01 January 1995

STP1291-EB: Applications of Inductively Coupled Plasma-Mass Spectrometry to Radionuclide Determinations - 01 January 1995

STP15985S: Determination of the Concentration and Isotopic Composition of Uranium in Environmental Air Filters - 01 January 1995

STP15986S: Analysis of Urine for U-235 and U-238 by ICP-MS - 01 January 1995

STP15976S: The Isotopic Ratio Measurement of Uranium in the Form of Hydrolyzed Uranium Hexafluoride by Inductively Coupled Plasma Multiple Collector Mass Spectrometry - 01 January 1995

STP15977S: Optimizing the Characterization of Iodine-129 and Technetium-99 in Radioactive Waste Using Inductively Coupled Plasma-Mass Spectrometry - 01 January 1995

STP15978S: Analysis of Radioactive Waste Samples by Ion Chromatography-beta-ICP-MS - 01 January 1995

STP15979S: Applications of Inductively Coupled Plasma-Mass Spectrometry to the Determination of Actinides and Fission Products in High Level Radioactive Wastes at the Savannah River Site - 01 January 1995

STP15980S: Ultra-Low Level (pg/L) Actinide Determinations and Superior Isotope Ratio Precisions by Quadrupole ICP-MS - 01 January 1995

STP15981S: Practical Comparison of Plasma Mass Spectrometry to Other Analytical Techniques for the Determination of Uranium Concentration and Isotopic Ratios in Industrial Waste Materials - 01 January 1995

STP15975S: The Comparison of Sample Preparation Techniques for the Determination of Technetium-99 in Pure Uranium Compounds and Subsequent Analysis by Inductively Coupled Plasma-Mass Spectrometry (ICP-MS) - 01 January 1995

STP15982S: Development of On-Line Electrochemical Sample Pretreatment Methods for the Analysis of Thallium and Uranium by ICP-MS - 01 January 1995

STP15983S: Determination of 230TH, 234U, 239PU, and 240PU in Soils by ICP-MS Using Flow-Injection Preconcentration - 01 January 1995

STP23986S: Effects of Cascade Damage and Helium Production Under 600 MeV Proton Irradiation of Cu and Cu-Al2O3 - 01 January 1994

STP1175-EB: Effects of Radiation on Materials: Sixteenth International Symposium - 01 January 1994

STP23987S: The Role of Nickel and Zinc in Defect Behavior and Microstructural Evolution of Copper Under Electron Irradiation - 01 January 1994

STP23988S: Mechanical Properties of Induction Brazed Glidcop Al-15 - 01 January 1994

STP23989S: The Response of Dispersion-Strengthened Copper Alloys to High Fluence Neutron Irradiation at 415°C - 01 January 1994

STP23930S: Strengthening of Chromium Films by 75 Mev Ni Ion Irradiation - 01 January 1994

STP23990S: Effects of Hot Implantation of Helium in Copper on Bubble Formation Within Grains and on Grain Boundaries - 01 January 1994

STP23991S: Evolution of Microstructure in Zirconium Alloy Core Components of Nuclear Reactors during Service - 01 January 1994

STP23992S: Modelling the Effect of Texture and Dislocation Structure on Irradiation Creep of Zirconium Alloys - 01 January 1994

STP23993S: Strain Hardening Parameter Evaluation of Irradiated Zircaloy—2 - 01 January 1994

STP23931S: Radiation Damage Rate Measurements in Nickel - 01 January 1994

STP23994S: Irradiation Growth of Zirconium Alloys - 01 January 1994

STP23995S: The Effect of Irradiation on the Mechanical Properties of 6061-T651 Aluminum - 01 January 1994

STP23996S: Effects of High Thermal Neutron Fluences on Type 6061 Aluminum - 01 January 1994

STP23997S: Irradiation-Induced Precipitation in Vanadium-Base Alloys Containing Titanium - 01 January 1994

STP23998S: Fatigue Crack Growth of Neutron Irradiated V-15Cr-5Ti and V-3Ti-1Si - 01 January 1994

STP23999S: Mechanical Properties of Vanadium Alloys Doped with Helium Using Various Techniques - 01 January 1994

STP24000S: Measurement of Electrical Conductivity of Ceramic Insulators in a Fission Reactor - 01 January 1994

STP24001S: Radiation Induced Mechanical Stresses in Polycrystalline Alumina Insulators - 01 January 1994

STP24002S: High-Temperature Irradiation of Alumina-Base Ceramic Materials in a Water Cooled Fission Reactor - 01 January 1994

STP24003S: The Effect of Neutron Irradiation on the Structure and Properties of Carbon-Carbon Composite Materials - 01 January 1994

STP24004S: Irradiation Behavior of Carbon-Boron-Titanium Materials - 01 January 1994

STP24005S: The Role of Phase-Boundary Fission-Gas Bubbles in the Cavitational Swelling of Irradiated U-Pu-Zr Fuel - 01 January 1994

STP24006S: Effect of Neutron Irradiation on Thermal Conductivity of Carbon/Carbon Fiber Materials at 400 and 600°C in the Fluence Range 1 × 1022 to 1 × 1024 m-2 - 01 January 1994

STP23932S: Effects of Fission and Fusion Neutron Irradiations on Mechanical Properties and Defect Recovery Behavior in α-Iron - 01 January 1994

STP1175-EB: Effects of Radiation on Materials: 16th International Symposium - 01 January 1994

STP23933S: Subsize Specimen Testing of a Nuclear Reactor Pressure Vessel Material - 01 January 1994

STP23924S: Usnrc Research on Reactor Pressure Vessel Steel Embrittlement - 01 January 1994

STP23934S: The Effect of Loading Rate Upon Irradiation Embrittlement Measured by Fracture Mechanical Properties - 01 January 1994

STP23935S: Effects Of Irradiation Temperature on Embrittlement of Nuclear Pressure Vessel Steels - 01 January 1994

STP23936S: Study on the Irradiation Embrittlement of a Microalloyed Ferritic Steel - 01 January 1994

STP23937S: Comparison of Drop-Weight and Instrumented Charpy Impact Test Results for Irradiated RPV Steels - 01 January 1994

STP23938S: Fracture Toughness and Impact Tests on Neutron Irradiated Ferritic Steels : Results and Correlations - 01 January 1994

STP23939S: Development and Application of an LWR Reactor Pressure Vessel-Specific Flaw Distribution - 01 January 1994

STP23940S: Effects of Irradiation Temperature on Charpy and Tensile Properties of High-Copper, Low Upper-Shelf, Submerged-Arc Welds - 01 January 1994

STP23941S: Evaluation of Thermal-Aged Plates, Forgings, and Submerged-Arc Weld Metals - 01 January 1994

STP23925S: Irradiation Creep due to SIPA Under Cascade Damage Conditions - 01 January 1994

STP23942S: Effect of Specimen Size on the Impact Properties of a Pressure Vessel Weld Material - 01 January 1994

STP23943S: Further Microstructural Characterization of Submerged-Arc Weld Metals - II - 01 January 1994

STP23944S: Exploratory Studies of the Effects of Irradiation Temperature on Mechanical Properties of Structural Steels amd Welds - 01 January 1994

STP23945S: The Radiation Hardening and Embrittlement of a Mild Steel Submerged-Arc Weld - 01 January 1994

STP23946S: Annealing Experiments on Irradiated NiCrMo Weld Metal - 01 January 1994

STP23947S: Degradation of Mechanical Properties of Stainless Steel Cladding Due to Neutron Irradiation and Thermal Aging - 01 January 1994

STP23948S: The Effect of Flux on the Irradiation Hardening of Pressure Vessel Steels - 01 January 1994

STP23926S: A Model for Interstitial Loop Formation in Concentrated Alloys During Irradiation - 01 January 1994

STP23949S: Modeling the Influence of Irradiation Temperature and Displacement Rate on Hardening Due to Point Defect Clusters in Ferritic Steels - 01 January 1994

STP23923S: Meeting Future Power Needs in Licensing Space - 01 January 1994

STP23950S: The Modelling of Radiation Hardening and Embrittlement in Magnox Mild Steel Submerged-Arc Welds - 01 January 1994

STP23951S: Irradiation Induced Precipitation in Model Alloys with Systematic Variation of Cu, Ni and P Content: A Small Angle Neutron Scattering Study - 01 January 1994

STP23952S: Characterisation of Model Fe-Cu-Mn-Ti-N Alloys by Electron Microscopy and Positron Annihilation - 01 January 1994

STP23953S: An APFIM Survey of Grain Boundary Segregation and Precipitation in Irradiated Pressure Vessel Steels - 01 January 1994

STP23954S: Investigation of Neutron Irradiated Soviet-type Reactor Pressure Vessel Steels by Small Angle Neutron Scattering - 01 January 1994

STP23955S: Influence of Some Alloying Elements on the Formation of Vacancy Defects in Ferritic Steels During Irradiation at 288°C - 01 January 1994

STP23956S: Metallurgical Considerations in the Application of DPA to Reactor Vessel Analysis - 01 January 1994

STP23957S: Postirradiation Deformation Behavior in Ferritic Fe-Cr Alloys - 01 January 1994

STP23927S: Predictions of Interfacial Phosphorus Segregation in Irradiated Ferritic Steels - 01 January 1994

STP23958S: Tensile and Fracture Mechanics Properties of Neutron Irradiated Manet I (Martensitic 11Cr Steel Type DIN 1.4914) - 01 January 1994

STP23959S: Influence of Cold Work, Heat Treatment, and Chromium Content on the Fracture Properties of Irradiated Martensitic Steels - 01 January 1994

STP23960S: Charpy Impact Toughness of Martensitic Steels Irradiated in FFTF: Effect of Heat Treatment - 01 January 1994

STP23961S: Microstructural Studies in Fast Reactor Irradiated FV448 Ferritic-Martensitic Alloy Plate and Weldment - 01 January 1994

STP23962S: Effects of Neutron Irradiation on the Notch Ductility of 15MnTi Steel - 01 January 1994

STP23963S: The Influence of Specimen Size on Measurement of Thermal or Irradiation Creep in Pressurized Tubes - 01 January 1994

STP23964S: Tensile Properties of Neutron Irradiated 316Ti and 15-15Ti Steels - 01 January 1994

STP23965S: Mechanical Property Degradation of Fast Reactor Fuel Cladding During Thermal Transients - 01 January 1994

STP23928S: Segregation Effects in Ferritic Fe-Cr Alloys - 01 January 1994

STP23966S: Fatigue Crack Growth Properties of Thermal Reactor Irradiated Nimonic PE16 - 01 January 1994

STP23967S: Influence of Cold Work on the Irradiation Creep and Creep Rupture of Titanium Modified Austenitic Stainless Steel - 01 January 1994

STP23968S: Mechanical Properties of 1950's Vintage Type 304 Stainless Steel Weldment Components After Low Temperature Neutron Irradiation - 01 January 1994

STP23969S: Effects of Neutron Irradiations at Temperatures Below 500°C on the Properties of Cold Worked 316 Stainless Steels: A Review - 01 January 1994

STP23970S: Technique to Eliminate Helium Induced Weld Cracking in Stainless Steels - 01 January 1994

STP23971S: Helium-Induced Weld Degradation of HT-9 Steel - 01 January 1994

STP23972S: The Complex Action of Major Solutes on Radiation-Induced Swelling of Fe-Cr-Ni Austenitic Alloys - 01 January 1994

STP23973S: Radiation Creep and Swelling of Austenitic 16Cr-15Ni-3Mo-Nb Steels Irradiated in the Reactor BOR-60 at 350 and 420 C - 01 January 1994

STP23974S: Swelling and Irradiation Creep of Neutron-Irradiated 316Ti and 15-15Ti Steels - 01 January 1994

STP23975S: Influence of Aluminum and Titanium on Gas Bubble Microstructure Formation in Nickel Under Helium-Ion Irradiation - 01 January 1994

STP23976S: Stress Corrosion Cracking Susceptibility of Irradiated Type 304 Stainless Steels - 01 January 1994

STP23977S: Radiation-Induced Solute Segregation and Stress Corrosion Cracking Study of AISI 304 and AISI 304L Stainless Steels - 01 January 1994

STP23978S: Influence of Impurities and Alloying Elements on IASCC in Neutron Irradiated Austenitic Stainless Steels - 01 January 1994

STP23979S: The Relationship of Grain Boundary Composition in Irradiated Type 304SS to Neutron Fluence and IASCC - 01 January 1994

STP23980S: Isotopic Tailoring with 59Ni to Study Helium Generation Rates and Their Effect on Tensile Properties of Neutron-Irradiated Fe-Cr-Ni Alloys - 01 January 1994

STP23981S: Microstructural and Microchemical Evolution During Fast Neutron Irradiation in Nickel and Nickel-Silicon Alloys Doped with Isotopically Controlled Boron - 01 January 1994

STP23929S: Neutron Irradiation Damage and Hardness Anisotropy in Molybdenum Single Crystals - 01 January 1994

STP23982S: The Effect of Phosphorus on the Microstructure of an Fe-16Cr-17Ni Austenitic Ternary Induced by Fast Neutron Irradiations - 01 January 1994

STP23983S: Void Formation and Induced-Segregation During Electron-Irradiation in Ti and Nb Modified Austenitic Steels - 01 January 1994

STP23984S: Effects of Applied Stress on Microstructural Evolution in 316SS Under Ion Irradiation - 01 January 1994

STP23985S: The Observation and Interpretation of Microstructural Evolution and Swelling in Austenitic Steels Under Irradiation - 01 January 1994

STP24878S: Application of Service Examinations to Transuranic Waste Container Integrity at the Hanford Site - 01 January 1994

STP24879S: High Level Nuclear Waste Management in U.S.A. - 01 January 1994

STP24880S: The Development of an Experimental Data Base for the Lifetime Predictions of Titanium Nuclear Waste Containers - 01 January 1994

STP24881S: Deterministic Predictions of Corrosion Damage to High Level Nuclear Waste Canisters - 01 January 1994

STP24882S: Approaches to Life Prediction for High-Level Nuclear Waste Containers in the Tuff Repository - 01 January 1994

STP24886S: Correlation of Autoclave Testing of Zircaloy-4 to In-Reactor Corrosion Performance - 01 January 1994

STP12794S: High Temperature Life Prediction of Monolithic Silicon Carbide Heat Exchanger Tubes - 01 January 1994

STP13704S: Application of J-Q Fracture Methodology to the Analysis of Pressurized Thermal Shock in Reactor Pressure Vessels - 01 January 1994

STP13732S: Fracture Capacity of High Flux Isotope Reactor (HFIR) Vessel with Random Crack Size and Toughness - 01 January 1994

STP15102S: Neutron Fluence Determination for Light Water Reactor Pressure Vessels - 01 January 1994

STP1228-EB: Reactor Dosimetry - 01 January 1994

STP15103S: Maine Yankee Dosimetry Capsule and Pressure Vessel Neutron Fluence Calculations - 01 January 1994

STP15104S: Analysis of PWR Pressure Vessel Surveillance Dosimetry with McBend - 01 January 1994

STP15105S: Special Dosimetry at Saint Laurent BL Mox-Loaded Unit - 01 January 1994

STP15106S: Three-Dimensional Discrete Ordinates Radiation Transport Calculations of Neutron Fluxes for Beginnig-of-Cycle at Several Pressure Vessel Surveillance Positions in the High Flux Isotope Reactor - 01 January 1994

STP15107S: Fluence Surveillance by Scraping Samples from the Inner Surface of the Thermal Shield in the Nuclear Power Plant Obrigheim in Germany (KWO). - 01 January 1994

STP15108S: Koeberg Surveillance Capsule Fluence Determination Using PCDC Dosimetry Cross Sections and Activation Measurements - 01 January 1994

STP15109S: Boron Determinations in Pressure Vessel Steels - 01 January 1994

STP15110S: Neutron Dosimetry with the 58Ni(n,p)58Co Reaction at Short-Decay Times - 01 January 1994

STP15111S: Mono-Energetic Mono-Directional Resonance Neutron Activation of Natural Indium Metal Target - 01 January 1994

STP15112S: Passive Temperature Monitoring in Reactor Environments Using Integrating Thermal Monitors - 01 January 1994

STP15093S: ASTM Standards Associated with PWR and BWR Power Plant Licensing, Operation and Surveillance - 01 January 1994

STP15113S: Neutron Flux Estimations Based on Niobium Impurities in Reactor Pressure Vessel Steel - 01 January 1994

STP15114S: Neutron Dosimetry and Mechanical Properties Changes Monitoring by Magnetic Response of Fe and Ni Wires - 01 January 1994

STP15115S: Applicability of Superheated Drop (Bubble) Detectors to Reactor Dosimetry - 01 January 1994

STP15116S: Materials Prepared at the Institute for Reference Materials and Measurements (IRMM) for Reactor Dosimetry Applications - 01 January 1994

STP15117S: Signal Anticipation of Rhodium Self Powered Neutron Detectors for On-Line Applications - 01 January 1994

STP15118S: Dynamic Compensation of the Silver Self-Powered Neutron Detector in the Ramp Program at the Osiris Reactor - 01 January 1994

STP15119S: Research for Application of Long Counter with a Position-Sensitive Proportional Counter to Neutron Dosimetry - 01 January 1994

STP15120S: The Modified Notched Neutron Spectrum Technique for the Surveillance of Hydrogen in Reactor Materials - 01 January 1994

STP15121S: Response Matrices of NE213 Scintillation Detectors for Neutrons - 01 January 1994

STP15122S: Accurate Neutron Fluence Measurements Using Bonner Spheres - 01 January 1994

STP15094S: VVER-440 Reactor Vessel Exposure Monitoring in the Czech Republic - 01 January 1994

STP15123S: Proton Recoil Spectroscopy 400 Meters from a Fission Neutron Source - 01 January 1994

STP15124S: Neutron Fluence Determination at Reactor Filters by 3He Proportional Counters: Comparison of Unfolding Algorithms - 01 January 1994

STP15125S: Analysis of the Venus Out-Of-Core Activation Measurements Using MCBEND - 01 January 1994

STP15126S: Analysis of the VENUS-1 Ex-Core Neutron Dosimetry Using the Lepricon Code System - 01 January 1994

STP15127S: Test Calculations of the Neutron Flux on VVER-1000 Reactor Pressure Vessel - 01 January 1994

STP15128S: Analysis of Pulsed-Sphere Experiments as Integral Data for Cross-Section Adjustment - 01 January 1994

STP15129S: Evaluation of the Results of the B&W Owners Group Cavity Dosimetry Benchmark Experiment - 01 January 1994

STP15130S: Neutron Leakage Benchmarks for Water Moderators - 01 January 1994

STP15131S: Pool Critical Assembly Benchmark Solutions Using MCNP and Threedant - 01 January 1994

STP15132S: Validation of Neutron Transport Calculations on Magnox Power Plant - 01 January 1994

STP15095S: Neutron Fluence Determination for WER-440 Reactor Pressure Vessel Ageing Surveillance - 01 January 1994

STP15133S: “Concrete Benchmark” Experiment as Support to Ex-Vessel LWR Surveillance Dosimetry - 01 January 1994

STP15091S: Impact of U.S. NRC Reactor Vessel Embrittlement Research on Regulation of Nuclear Power Plants - 01 January 1994

STP15134S: The Materials Dosimetry Reference Facility - 01 January 1994

STP15135S: SILENE, a New Radiation Reference Source - 01 January 1994

STP15136S: Development of an Alanine Dosimeter for Gamma Dosimetry in Mixed Environments - 01 January 1994

STP15137S: Reusability of CaF2:Mn Thermoluminescence Dosimeters for Photon Irradiations at High Absorbed-Dose Levels - 01 January 1994

STP15138S: Gamma-Ray Dose Mapping in Operational CANDU Reactor Containment Areas Using MOS Dosimeters - 01 January 1994

STP15139S: Characterization of the Gamma Field in the B%W Owners Group Cavity Dosimetry Benchmark Experiment - 01 January 1994

STP15140S: Measurement and Analysis of Gamma-Ray Distributions in Kyoto University Critical Assembly, KUCA - 01 January 1994

STP15096S: Revision of Neutron Dosimetry for the Loviisa WER-440 Reactors: Principles and Application - 01 January 1994

STP15141S: Overview of the Activities in Spain on Irradiation Embrittlement of RPV Steel - 01 January 1994

STP15142S: Neutron Spectrum Effect on Pressure Vessel Embrittlement: Dosimetry and Qualification of Irradiation Locations in Osiris and Siloe Reactors - 01 January 1994

STP15143S: The Irradiation Facility Korpus for Irradiation of the Reactor Structure Materials - 01 January 1994

STP15144S: Reactor Vessel Dosimetry Assessment: Perspectives of the Materials Engineer - 01 January 1994

STP15145S: Calculation of Transmutation in Copper and Comparison with Measured Electrical Properties - 01 January 1994

STP15146S: Intercomparison of Neutron Test Facilities for Equivalent Damage to Electronics - 01 January 1994

STP15147S: The Test Reactor Embrittlement Data Base (TR-EDB) - 01 January 1994

STP15148S: Calculated Damage Rates for FFTF Structural Components and Surveillance Assemblies - 01 January 1994

STP15149S: A Plant-Specific Upper Shelf Energy Drop Methodology - 01 January 1994

STP15150S: Calculated and Measured Gas Formation in Beryllium Samples Irradiated in the High Flux Materials Testing Reactor BR2 - 01 January 1994

STP15151S: The Spallation Neutron Source SINQ and Related Dosimetry Problems - 01 January 1994

STP15097S: Pressure Vessel Fluence Monitoring at NPP with VVER: Routine Technique and New Approaches - 01 January 1994

STP15152S: Dosimetry Issues for an Ultra-High Flux Beam and Multipurpose Research Reactor Design - 01 January 1994

STP15153S: Investigation of Laboratory Neutron Spectral Characterizations Used for the Testing of Electronic Parts - 01 January 1994

STP15154S: Dosimetry Aspects of the New Canadian MAPLE-X10 Reactor - 01 January 1994

STP15155S: Neutron Metrology in the Fuel Assemblies of a Material Test Reactor. - 01 January 1994

STP15156S: Two-Dimensional Neutron and Gamma Calculations for Devices Irradiated in BR2 Reflector Positions - 01 January 1994

STP15157S: Energy and Spatial Distribution of the Photoneutron Flux from a Radiotherapy Electron Accelerator - 01 January 1994

STP15158S: Determination of the Neutron Flux for the Yankee Rowe Experiment in the Ford Nuclear Reactor - 01 January 1994

STP15159S: Testing of the IRDF-90 Cross-Section Library in Benchmark Neutron Spectra - 01 January 1994

STP15160S: Comparison of the BUGLE-80 and SAILOR Libraries for Coupled Neutron-Gamma Transport Applications - 01 January 1994

STP15098S: Analysis of the TIHANGE-2 Surveillance Neutron Dosimetry Using the Lepricon Code System - 01 January 1994

STP15161S: Production and Testing of the Vitamin-B6 Fine-Group and the BUGLE-93 Broad-Group Neutron/Photon Cross-Section Libraries Derived from ENDF/B-VI Nuclear Data - 01 January 1994

STP15162S: JENDL Dosimetry File - 01 January 1994

STP15163S: Status of Neutron Dosimetry Cross Sections - 01 January 1994

STP15164S: Nuclear Data Needs for Fission Reactor Decommissioning - 01 January 1994

STP15165S: Evaluation of the 93Nb(n,n') 93mNb and 93Nb(n,2n) 92mNb Reactions Cross-Sections from Threshold to 20 MEV. - 01 January 1994

STP15166S: Measurements of the 237Np(n,f) Cross Section - 01 January 1994

STP15167S: Measurements of Thermal Neutron Cross Section and Resonance Integral for the 237Np(n,γ)238Np Reaction - 01 January 1994

STP15168S: Measurement of 233U Fission Spectrum-Averaged Cross Sections for Some Threshold Reactions - 01 January 1994

STP15169S: Calculation of Cobalt and Gold Dosimetry Cross Sections from 1 to 50 MeV - 01 January 1994

STP15170S: Measurement and Analysis of the Nitrogen Total and Differential Scattering Cross Sections in the Resonance Region - 01 January 1994

STP15171S: Effect of Gadolinium Covers on Fast Dosimeter Response - 01 January 1994

STP15172S: The DS86 Neutron Dosimetry Enigma: Some Missing Pieces to the Puzzle - 01 January 1994

STP15099S: Lepricon, Combination of Correlated Data and Peelle's Puzzle - 01 January 1994

STP15173S: Helium Measurements in Support of MHTGR Lithium Target Testing - 01 January 1994

STP15174S: Design of a Target and Moderator at the Los Alamos Spallation Radiation Effects Facility (LASREF) as a Neutron Source for Fusion Reactor Materials Development - 01 January 1994

STP15175S: Spallation Radiation Damage and Dosimetry for Accelerator Transmutation of Waste Applications - 01 January 1994

STP15176S: Neutron Dosimetry and Activation on the Tokamak Tore-Supra - 01 January 1994

STP15177S: Dosimetry of Medium Energy Neutrons and Protons in Material Irradiation Experiments - 01 January 1994

STP15178S: Neutron Cross Sections for the Interpretation of a Spallation Experiment - 01 January 1994

STP15100S: Assessment of Uncertainty in Reactor Vessel Fluence Determination - 01 January 1994

STP15101S: Investigations into Power Reactor Fluence Uncertainties and their Implications for Trend Curves - 01 January 1994

STP15092S: Technical Issues Relevant to ASTM LWR Surveillance Standards - 01 January 1994

STP13964S: Fatigue and Fracture Analysis of Type 316L Thin-Walled Piping for Heavy Water Reactors: Crack Growth Prediction Over 60 Years (With and Without Stratification) and Flawed Pipe Testing - 01 January 1994

STP13966S: Optimum Fracture Control Plan for Gas Turbine Engine Components - 01 January 1994

STP15187S: Growth and Characterization of Oxide Films on Zirconium-Niobium Alloys - 01 January 1994

STP1245-EB: Zirconium in the Nuclear Industry: Tenth International Symposium - 01 January 1994

STP15188S: Correlation Between Irradiated and Unirradiated Fracture Toughness of Zr-2.5Nb Pressure Tubes - 01 January 1994

STP15189S: Variability of Irradiation Growth in Zr-2.5Nb Pressure Tubes - 01 January 1994

STP15190S: Change of Mechanical Properties by Irradiation and Evaluation of the Heat-Treated Zr-2.5Nb Pressure Tube - 01 January 1994

STP15182S: Zirconium Alloy Performance in Light Water Reactors: A Review of UK and Scandinavian Experience - 01 January 1994

STP15191S: On the Anisotropy of In-Reactor Creep of Zr-2.5Nb Tubes - 01 January 1994

STP15192S: Fabrication of Zr-2.5Nb Pressure Tubes to Minimize the Harmful Effects of Trace Elements - 01 January 1994

STP15193S: Modeling of Damage in Cold Pilgering - 01 January 1994

STP15194S: Mitigation of Harmful Effects of Welds in Zirconium Alloy Components - 01 January 1994

STP15195S: Fabrication Process of High Nodular Corrosion-Resistant Zircaloy-2 Tubing - 01 January 1994

STP15196S: Corrosion Behavior of Zircaloy-4 Sheets Produced Under Various Hot-Rolling and Annealing Conditions - 01 January 1994

STP15197S: Optimization of PWR Behavior of Stress-Relieved Zircaloy-4 Cladding Tubes by Improving the Manufacturing and Inspection Process - 01 January 1994

STP15198S: Experimental and Theoretical Studies of Parameters that Influence Corrosion of Zircaloy-4 - 01 January 1994

STP15183S: The Effect of Fluence and Irradiation Temperature on Delayed Hydride Cracking in Zr-2.5Nb - 01 January 1994

STP15199S: Aqueous Chemistry of Lithium Hydroxide and Boric Acid and Corrosion of Zircaloy-4 and Zr-2.5Nb Alloys - 01 January 1994

STP15181S: Development of Zirconium-Barrier Fuel Cladding - 01 January 1994

STP15200S: Corrosion Behavior of Irradiated Zircaloy - 01 January 1994

STP15201S: Correlation of Transmission Electron Microscopy (TEM) Microstructure Analysis and Texture with Nodular Corrosion Behavior for Zircaloy-2 - 01 January 1994

STP15202S: Micro-Characterization of Corrosion Resistant Zirconium-Based Alloys - 01 January 1994

STP15203S: An Experimental Investigation into the Oxidation of Zircaloy-4 at Elevated Pressures in the 750 to 1000°C Temperature Range - 01 January 1994

STP15204S: Prediction of Creep Anisotropy in Zircaloy Cladding - 01 January 1994

STP15205S: Microstructure and Properties of Corrosion-Resistant Zirconium-Tin-lron-Chromium-Nickel Alloys - 01 January 1994

STP15206S: Fatigue Behavior of Irradiated and Unirradiated Zircaloy and Zirconium - 01 January 1994

STP15207S: Effect of Irradiation on the Microstructure of Zircaloy-4 - 01 January 1994

STP15208S: Irradiation Effect on Fatigue Behavior of Zircaloy-4 Cladding Tubes - 01 January 1994

STP15209S: Grain-by-Grain Study of the Mechanisms of Crack Propagation During Iodine Stress Corrosion Cracking of Zircaloy-4 - 01 January 1994

STP15210S: Microstructure of Oxide Layers Formed During Autoclave Testing of Zirconium Alloys - 01 January 1994

STP15211S: Corrosion Performance of New Zircaloy-2-Based Alloys - 01 January 1994

STP15212S: Examinations of the Corrosion Mechanism of Zirconium Alloys - 01 January 1994

STP15184S: A Study of the Hydrogen Uptake Mechanism in Zirconium Alloys - 01 January 1994

STP15213S: On the Initial Corrosion Mechanism of Zirconium Alloy: Interaction of Oxygen and Water with Zircaloy at Room Temperature and 450°C Evaluated by X-Ray Absorption Spectroscopy and Photoelectron Spectroscopy - 01 January 1994

STP15214S: How the Tetragonal Zirconia is Stabilized in the Oxide Scale that is Formed on a Zirconium Alloy Corroded at 400°C in Steam - 01 January 1994

STP15215S: Oxidation of Intermetallic Precipitates in Zircaloy-4: Impact of Irradiation - 01 January 1994

STP15216S: Corrosion Optimized Zircaloy for Boiling Water Reactor (BWR) Fuel Elements - 01 January 1994

STP15217S: In-Reactor Corrosion Performance of ZIRLO™ and Zircaloy-4 - 01 January 1994

STP15218S: Phenomenological Study of In-Reactor Corrosion of Zircaloy-4 in Pressurized Water Reactors - 01 January 1994

STP15219S: Corrosion Behavior of Zircaloy-4 Cladding with Varying Tin Content in High-Temperature Pressurized Water Reactors - 01 January 1994

STP15220S: Effects of Pressurized Water Reactor (PWR) Coolant Chemistry on Zircaloy Corrosion Behavior - 01 January 1994

STP15185S: Hydrogen Absorption Kinetics During Zircaloy Oxidation in Steam - 01 January 1994

STP15186S: Scanning Electron Microscope Techniques for Studying Zircaloy Corrosion and Hydriding - 01 January 1994

STP13990S: Equating Damped Vibration to Constant Amplitude Fatigue Loading for a Thick-Walled Pressure Vesselz - 01 January 1994

STP13992S: Fatigue Life Prediction for Wind Turbines: A Case Study on Loading Spectra and Parameter Sensitivity - 01 January 1994

STP24768S: B&W Owners Group Master Integrated Reactor Vessel Surveillance Program - 01 January 1993

STP1170-EB: Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Fourth Volume) - 01 January 1993

STP24769S: Study by Positron Annihilation of Neutron Damage in a Pressurized Water Reactor (PWR) Pressure Vessel Steel After a 13-Year Irradiation in the CHOOZ A Reactor Surveillance Program - 01 January 1993

STP24770S: Surveillance Dosimetry of the French 900-MW Pressurized Water Reactors (PWRs): Results, Uncertainties, and Reactor Series Effects - 01 January 1993

STP24771S: Analysis of the Results from the Surveillance Specimen Program for Reactor Pressure Vessels of Nuclear Power Plant W-2 in Jaslovské Bohunice - 01 January 1993

STP24772S: Fracture Properties of Irradiated A533B,Cl.1, A508,Cl.3, and 15Ch2NMFAA Reactor Pressure Vessel Steel - 01 January 1993

STP24773S: Radiation Embrittlement and Annealing Recovery of CrNiMoV Pressure Vessel Steels with Different Copper and Phosphorus Content - 01 January 1993

STP24774S: Investigation on the Impact Strength and Toughness of A533 Grade B Composition Weld Metal Using Small Specimens - 01 January 1993

STP24775S: Influence of Specimen Orientation on the Upper Shelf Energy and Transition Temperature Shift of Reactor Pressure Vessel Steel Base Metal - 01 January 1993

STP24776S: Mechanical and Nondestructive Testing of Irradiated Half Charpy Specimens - 01 January 1993

STP24777S: Radiation Embrittlement of Soviet 1000-MW Pressurized Water Reactor Vessel Steel 15KH2NMFAA - 01 January 1993

STP24778S: Radiation Effects on the Mechanical Properties of SA 508 Cl.3 Forging - 01 January 1993

STP24779S: Irradiation Response of the IAEA CRP-3 Material FFA Measured by Fracture Toughness Specimens - 01 January 1993

STP24780S: Analysis of Radiation Embrittlement Results from a French Forging Examined in the Second Phase of an IAEA-Coordinated Research Program - 01 January 1993

STP24781S: Interactions of Defects with Dislocations in Reactor Pressure Vessel Steels - 01 January 1993

STP24782S: Influence of Phosphorus on Thermal and Neutron Embrittlement of Pressure Vessel Steels - 01 January 1993

STP24783S: Influence of Neutron Irradiation on the Microstructure and Mechanical Properties of 15Kh2MFA Steel - 01 January 1993

STP24760S: Management of Neutron Radiation Embrittlement: A View from the United States - 01 January 1993

STP24784S: Neutron Fluence Management to Optimize Pressure Vessel Lifetime - 01 January 1993

STP24785S: Evaluation of the Recovery Annealing of the Reactor Pressure Vessel of NPP Nord (Greifswald) Units 1 and 2 by Means of Subsize Impact Specimens - 01 January 1993

STP24786S: Irradiation and Annealing Behavior of 15Kh2MFA Reactor Pressure Vessel Steel - 01 January 1993

STP24787S: Recovery of the Transition Temperature of Irradiated WWER-440 Vessel Metal by Annealing - 01 January 1993

STP24788S: Thermal Annealing of the Reactor Pressure Vessel NPP Unit 2 in Jaslovské Bohunice for Its Radiation Embrittlement Regeneration - 01 January 1993

STP24789S: Sensitivity Analysis of Thermal and Stress Fields in the Core Belt of a Pressurized Water Reactor - 01 January 1993

STP24761S: Radiation Embrittlement of Spanish Nuclear Reactor Pressure Vessel Steels - 01 January 1993

STP24762S: Analysis of the Surveillance Results at Paks Nuclear Power Plant - 01 January 1993

STP24763S: Surveillance of WWER-440Č Reactor Pressure Vessels - 01 January 1993

STP24764S: Surveillance Data on Neutron Embrittlement of Modern Low-Sensitivity Steel - 01 January 1993

STP24765S: A Utility Perspective on Management of Reactor Pressure Vessel Embrittlement - 01 January 1993

STP24766S: Utilization of Reactor Pressure Vessel Surveillance Data in Support of Aging Management - 01 January 1993

STP24767S: An Overview of Radiation Embrittlement Modeling for Reactor Vessel Steels - 01 January 1993

STP24759S: Radiation Stability of WWER-440 Vessel Materials - 01 January 1993

STP18025S: Influence of Crack Depth on the Fracture Toughness of Reactor Pressure Vessel Steel - 01 January 1993

STP18030S: Specimen Size Effects on J-R Curves for RPV Steels - 01 January 1993

STP24255S: Thermomechanical Fatigue of Turbo-Engine Blade Superalloys - 01 January 1993

STP24258S: Prediction of Thermal-Mechanical Fatigue Life for Gas Turbine Blades in Electric Power Generation - 01 January 1993

STP24278S: Fracture Properties of Specially Heat-Treated ASTM A508 Class 2 Pressure Vessel Steel - 01 January 1993

STP24815S: Multiaxial Low-Cycle Fatigue Evaluations of Pressure Vessel Components - 01 January 1993

STP12724S: Application of Micromechanical Material Models for the Evaluation of the Fracture Toughness of Primary Circuit Steel Components - 01 January 1993

STP1204-EB: Small Specimen Test Techniques Applied to Nuclear Reactor Vessel Thermal Annealing and Plant Life Extension - 01 January 1993

STP12725S: On the Brittle-to-Ductile Transition Fracture Behavior - 01 January 1993

STP12726S: Fracture Toughness Measurements with Subsize Disk Compact Specimens - 01 January 1993

STP12727S: On the Development of a Fracture Toughness Test Procedure Using a Notched Disk Specimen - 01 January 1993

STP12728S: Assessment of Fracture Toughness by a Punch Test with Miniature Specimens - 01 January 1993

STP12718S: Electrochemical Evaluation of Thermal Aging Embrittlement of 2 1/4Cr-1Mo Steel for a Nuclear Pressure Vessel - 01 January 1993

STP12729S: Fracture Toughness Evaluation for Zircaloy-2 Pressure Tubes with the Electric-Potential Method - 01 January 1993

STP12730S: Miniaturized Fracture Toughness Testing During the Plant Life Extension Period - 01 January 1993

STP12731S: Estimation of Toughness Degradation by Microhardness and Small Punch Tests - 01 January 1993

STP12732S: Hardening Characteristics of Ion-Irradiated Iron-Based Model Alloys - 01 January 1993

STP12733S: Development of a Miniaturized Bulge Test (Small Punch Test) for Post-Irradiation Mechanical Property Evaluation - 01 January 1993

STP12734S: Evaluation of Tensile Properties Using a TEM Disk-Size Specimen - 01 January 1993

STP12735S: Development of a Miniature-Disk Bending Fatigue Specimen - 01 January 1993

STP12736S: Two Micro Fatigue Test Methods for Irradiated Materials - 01 January 1993

STP12719S: In-Situ Measurements of Mechanical Properties Using Novel Automated Ball Indentation System - 01 January 1993

STP12737S: Methods and Devices for Small Specimen Testing at the Japan Atomic Energy Research Institute - 01 January 1993

STP12738S: Evaluating a Service-Exposed Component's Mechanical Properties by Means of Subsized and Miniature Specimens - 01 January 1993

STP12739S: Tension Test System for Irradiated Small Specimens Operated by Remote Control - 01 January 1993

STP12740S: Application of Miniature Tension Specimens to Studies of Radiation Damage in Metals - 01 January 1993

STP12741S: An Automated Tensile Machine for Small Specimens Heavily Neutron Irradiated in FFTF/MOTA - 01 January 1993

STP12742S: Evaluation of Miniature Tension Specimen Fabrication Techniques and Performance - 01 January 1993

STP12743S: A Novel Miniature Tension Test Machine - 01 January 1993

STP12744S: Application of Subsize Specimens in Nuclear Plant Life Extension - 01 January 1993

STP12745S: Investigation of Material Behavior Under Reirradiation after Annealing Using Subsize Specimens - 01 January 1993

STP12746S: Use of Subsize Specimens for Determination of Radiation Embrittlement of Operating Reactor Pressure Vessels - 01 January 1993

STP12747S: Application of Reconstitution Welding Technique for Studying Base Metal of a Novovoronesh Unit-1 Trepan Sample - 01 January 1993

STP12720S: Recent Improvements in Size Effects Correlations for DBTT and Upper Shelf Energy of Ferritic Steels - 01 January 1993

STP12717S: Pressure Vessel Steel Embrittlement Monitoring by Magnetic Properties Measurements - 01 January 1993

STP12721S: Laser Weld Reconstitution of Conventional Charpy and Miniaturized Notch Test (MNT) Specimens - 01 January 1993

STP12722S: Fracture Toughness Evaluation of Neutron-Irradiated Composites by a Miniaturized Charpy Test - 01 January 1993

STP12723S: Simple Constraint Corrections for Subsize Fracture Toughness Specimens - 01 January 1993

STP12754S: SSRT for Hydrogen Water Chemistry Verification in BWRs - 01 January 1993

STP12755S: Applications of Slow Strain Rate Testing in the Nuclear Power Industry - 01 January 1993

STP12756S: Measurement of the Deformability of Austenitic Stainless Steels and Nickel-Base Alloys in Light Water Reactor Cores - 01 January 1993

STP24175S: Fatigue Lifetime Monitoring in Power Plants - 01 January 1992

STP24176S: Fatigue Analysis Techniques for Vintage Steam Turbine/Generator Components - 01 January 1992

STP17927S: The Influence on Nickel Content on Microstructures of Fe-Cr-Ni Austenitic Ternaries Irradiated with Fast Neutrons or Heavy Ions - 01 January 1992

STP1125-EB: Effects of Radiation on Materials: 15th International Symposium - 01 January 1992

STP17928S: The Behavior of Irradiation-Produced Dislocation Loops under External Stress during Electron Irradiation - 01 January 1992

STP17929S: Simulation Study of Low-Temperature Irradiation and a LOCA and the Resulting Microstructural Changes in 316 Stainless Steel - 01 January 1992

STP17930S: Surface Modification of Austenitic 304 Stainless Steel by N+2 and 11+B Ion Implantation - 01 January 1992

STP17931S: Transient and Static Mechanical Properties of D9 Fuel Pin Cladding and Duct Material Irradiated to High Fluence - 01 January 1992

STP17932S: Effect of Hold Time and Frequency on the Fatigue Crack Growth Rate of Irradiated Cold-Worked Type 316 Stainless Steel - 01 January 1992

STP17933S: Comparison of Small-Scale Bending and Axial Fatigue Specimens - 01 January 1992

STP17934S: Characterization of 316L Steel-Welded Joints Irradiated Between 15 and 41 dpa - 01 January 1992

STP17935S: Effect of Microalloying with Boron and Rare-Earth Metals on Swelling and Mechanical Properties of Fe-16Cr-15Ni Steels - 01 January 1992

STP17936S: Comparison of the Effects of Long-Term Thermal Aging and HFIR Irradiation on the Microstructural Evolution of 9Cr-1MoVNb Steel - 01 January 1992

STP17937S: Radiation Damage Studies of the 10 to 13% Chromium-Containing Steels and Alloys Irradiated with Heavy Ions - 01 January 1992

STP17938S: A Comparison of Heavy Ion-Irradiated Ferritic and Austenitic Steels in the Early Stages of Damage - 01 January 1992

STP17865S: Evolution of the Microstructure of PWR Pressure Vessel Steels from the CHOOZ A Reactor Surveillance Program after Long-Term Irradiations - 01 January 1992

STP17939S: The Effect of Neutron Irradiation on the Microstructure and Tensile Properties of 1 Cr13Mo2NbVB Steel - 01 January 1992

STP17940S: Precipitation Evolution in HT-9 Steel Under Thermal Aging and Stress Rupture Conditions - 01 January 1992

STP17941S: Behavior under Neutron Irradiation of the 15-15Ti and EM10 Steels Used as Standard Materials of the Phénix Fuel Subassembly - 01 January 1992

STP17942S: Postirradiation Strength and Deformation of Ferritic Fe-Cr Binary Alloys - 01 January 1992

STP17943S: Ductility and Hardening of Neutron-Irradiated Fe-Cr and Fe-Cr-Ni Steels - 01 January 1992

STP17944S: Irradiation Effects on Impact Behavior of 12Cr-1MoVW and 2¼Cr-1Mo Steels - 01 January 1992

STP17945S: Fracture Toughness and Tensile Properties of Alloy HT9 in Thin Sections under High Neutron Fluences - 01 January 1992

STP17946S: Evaluation of Irradiation Embrittlement of 2¼Cr-1Mo Steel in Terms of Elastic-Plastic Fracture Toughness - 01 January 1992

STP17858S: The Design and Performance of High-Temperature Irradiation Capsules - 01 January 1992

STP17947S: Effect of Neutron Irradiation on the Mechanical Properties of Microalloyed Steel for Reinforced Cement Concrete - 01 January 1992

STP17866S: The Structure and Hardening Mechanism of Copper Precipitation in Thermally Aged or Irradiated Fe-Cu and Fe-Cu-Ni Model Alloys - 01 January 1992

STP17867S: The Effects of Metallurgical and Irradiation Variables on the Postirradiation Annealing Kinetics of Pressure Vessel Steels - 01 January 1992

STP17868S: Irradiation Response and Annealing Behavior of Pressure Vessel Model Steels and Iron Ternary Alloys Measured with Positron Techniques - 01 January 1992

STP17869S: Further Microstructural Characterization of Submerged-Arc Weld Metals - 01 January 1992

STP17870S: Irradiation Response of the New IAEA Correlation Monitor Material JRQ Measured by Fracture Mechanical Properties - 01 January 1992

STP17871S: An Alternative Approach for the Use of Surveillance Program Results - 01 January 1992

STP17872S: Application of Reference Toughness Curves to the HSSI Fifth Irradiation Series - 01 January 1992

STP17859S: In-Service Evaluation of French Pressurized Water Reactor Vessel Steel - 01 January 1992

STP17873S: Effects of Irradiation on Crack-Arrest Toughness of Two High-Copper Welds - 01 January 1992

STP17874S: Statistical Analyses of Fracture Toughness Results for Two Irradiated High-Copper Welds - 01 January 1992

STP17875S: Irradiation Characteristics of Weld Wire Heat Number 72105 - 01 January 1992

STP17876S: Mechanical Property Evaluation of Rajasthan Atomic Power Station Coolant Channel Components - 01 January 1992

STP17877S: Rejuvenation of Fracture Properties of Irradiated Zr-2.5 Nb by Heat Treatment - 01 January 1992

STP17878S: Impression Testing to Determine the Effects of Recrystallization and Radiation on the Deformation Anisotropy of Zircaloy TREX - 01 January 1992

STP17879S: Effects of Proton Irradiation on the Microstructural Evolution of Zircaloy-2 Tubing - 01 January 1992

STP17880S: Cascade Collapse in Copper and Nickel - 01 January 1992

STP17881S: Cascade Damage in Alpha-Titanium - 01 January 1992

STP17857S: Calculated Production of High-Energy Neutrons by 800-MeV Protons - 01 January 1992

STP17882S: Radiation-Induced Order-Disorder Transformation and Recovery in Copper-Palladium - 01 January 1992

STP17883S: Defect Production Efficiency in Neutron-Irradiated Iron - 01 January 1992

STP17884S: Instability of Spatially Homogenous Interstitial Solution and Interstitial Cluster Nucleation on Initial Stage of Irradiation - 01 January 1992

STP17885S: The Interaction of Point Defects with Line Dislocations in HVEM Irradiated Fe-Ni-Cr Alloys - 01 January 1992

STP17886S: Effects of Internal Hydrogen on the Vacancy Loop Formation Probability in Aluminum - 01 January 1992

STP17887S: Production and Annealing of Radiation Defects in Scandium-Doped Austenitic Fe-Cr-Ni Alloys - 01 January 1992

STP17888S: Early Stages of the Evolution of Bubbles in an Aluminum-40 At% Manganese Alloy During Argon Ion Irradiation - 01 January 1992

STP17889S: Helium Bubbles in Titanium-Stabilized Austenitic Stainless Steels Investigated by Positron Annihilation Spectroscopy - 01 January 1992

STP17890S: Brittle Fracture of Material Due to Growing Pressurized Cracks - 01 January 1992

STP17860S: Neutron Irradiation Embrittlement of Pressure Vessel Materials in Spanish Nuclear Power Reactors - 01 January 1992

STP17891S: A Theoretical Model of Accelerated Irradiation Creep at Low Temperatures by Transient Interstitial Absorption - 01 January 1992

STP17892S: Dislocation Core Microstructure and Its Effect on Irradiation Creep - 01 January 1992

STP17893S: Irradiation Creep by Glide-Induced Transient Absorption - 01 January 1992

STP17894S: Diffusion Growth Rate of Macrodefects in Ensembles - 01 January 1992

STP17895S: An Account of Point-Defect Recombination in the Theory of Void Swelling - 01 January 1992

STP17861S: Evaluation of Tarapur Atomic Power Station Pressure Vessel Surveillance Results - 01 January 1992

STP17896S: Spatial Self-Organization of a Void System in Irradiated Metals - 01 January 1992

STP17897S: Auto-Oscillation Process in Impure Crystals under Irradiation - 01 January 1992

STP17898S: Radiation-Induced Segregation in 20Cr/25Ni/Nb Stainless Steel - 01 January 1992

STP17899S: Irradiation-Induced Microchemical Effects and IASCC Initiation - 01 January 1992

STP17900S: Interfacial Segregation in Fast Reactor Irradiated 12% Chromium Martensitic Steel - 01 January 1992

STP17901S: The Effect of Neutron Irradiation on Segregation to Grain Boundaries in Nimonic PE16 - 01 January 1992

STP17862S: Mechanical Testing of Civil Advanced Gas-Cooled Reactor Tie Bars - 01 January 1992

STP17902S: Microstructural Characterization of Irradiated Nimonic PE16 - 01 January 1992

STP17903S: Segregation of Tin in Zircaloy-2 under Proton Irradiation - 01 January 1992

STP17904S: X-Ray Analysis of the Surface Alloy Formed by High-Dose Implantation of Iron in Aluminum - 01 January 1992

STP17905S: Radiation-Modified Phase Diagrams of Binary Alloys - 01 January 1992

STP17906S: The Defect Structure of Ion and Neutron Irradiated YBa2Cu3O7-δ Single Crystals - 01 January 1992

STP17907S: The Effect of Crystal Orientation on Damage Accumulation in Chromium-Implanted Al2O3 - 01 January 1992

STP17908S: Dislocation Loop Formation in Ion-Irradiated Polycrystalline Spinel and Alumina - 01 January 1992

STP17909S: Radiation Damage in Fusion Window Materials Studied by Thermal Conductivity - 01 January 1992

STP17863S: Reconstituted Impact Specimens with Small Inserts - 01 January 1992

STP17910S: Electrical Conductivity of Single Crystal α-Alumina under Neutron and γ-Ray Irradiation - 01 January 1992

STP17911S: Effects of Neutron Irradiation on Ceramics Fiber-Reinforced Composites - 01 January 1992

STP17912S: Mechanistic Interpretation of an Observed Fission-Rate Dependence of Low-Temperature Swelling of Irradiated Uranium Silicide Dispersion Fuels - 01 January 1992

STP17913S: A Brief Review of Radiation-Induced Cavity Swelling and Hardening in Copper and Copper Alloys - 01 January 1992

STP17914S: Unusual Tensile and Fracture Behavior of Pure Copper at High Levels of Neutron-Induced Swelling - 01 January 1992

STP17915S: Tensile Behavior of Cu-5Ni and Various Precipitation-Strengthened Copper Alloys after High-Fluence Irradiation - 01 January 1992

STP17916S: Mechanical Property Changes and Microstructures of Dispersion-Strengthened Copper Alloys after Neutron Irradiation at 411, 414, and 529°C - 01 January 1992

STP17917S: Positron Lifetime Studies of Helium Bubble Kinetics in Alpha-Irradiated Copper - 01 January 1992

STP17918S: Relationship of Microstructure and Tensile Properties for Neutron-Irradiated Vanadium Alloys - 01 January 1992

STP17919S: Vanadium Alloys with Improved Resistance to Helium Embrittlement - 01 January 1992

STP17920S: Effect of Helium and dpa's on Tensile Properties of V-5Ti and V-3Ti-1Si - 01 January 1992

STP17921S: Large Swelling Observed in a V-5at%Fe Alloy After Irradiation in FFTF - 01 January 1992

STP17864S: Investigations of Gundremmingen RPV Archive Material Irradiated in Light-Water and Heavy-Water Reactors - 01 January 1992

STP17922S: A Contribution to the Phase Diagram of Fe-Mn-Cr Alloys - 01 January 1992

STP17923S: Microstructural Examination of Fe-Cr-Mn Alloys after Charged Particle Irradiation - 01 January 1992

STP17924S: The Effects of Nickel on Microstructural Development and Microchemical Changes in Neutron-Irradiated Fe-Cr-Mn Based Steels - 01 January 1992

STP17925S: Ion Irradiation Effects on a Martensitic Stainless Steel Designed for Reduced Long-Life Radioactivity - 01 January 1992

STP17926S: The Effect of Phosphorus on the Radiation-Induced Microstructure of Stabilized Austenitic Stainless Steels - 01 January 1992

STP19729S: Design and Construction of Cement-Bentonite Cutoff Wall for S.A. Murray Jr. Hydroelectric Station - 01 January 1992

STP15518S: Fracture Resistance of a Pressure Vessel Steel Under Impact Loading Conditions - 01 January 1992

STP15513S: Lower-Bound Initiation Toughness of A533-B Reactor-Grade Steel - 01 January 1992

STP15531S: Gas Reburning—Sorbent Injection for the Control of Acid Rain Precursors from Coal Fired Utility Boilers - 01 January 1992

STP15856S: Georgia Power Company Acoustic Emission Test Program - 01 January 1992

STP1139-EB: Acoustic Emission Testing of Aerial Devices and Associated Equipment Used in the Utility Industries - 01 January 1992

STP15857S: An Acoustic Emissions Testing Program - 01 January 1992

STP15858S: Acoustic Emission Monitoring and Destructive Testing of Glass Fibre Reinforced Plastic Bucket Truck Booms - 01 January 1992

STP15859S: Analysis of ASTM Round-Robin Results: Ae Sensors, Systems, Brands, and Calibration Rods - 01 January 1992

STP15860S: Personnel Qualification and Certification for Acoustic Emission Testing of Aerial Devices - 01 January 1992

STP15861S: Advances in AE Technology for Testing of Aerial Devices - 01 January 1992

STP23761S: Data for the Stepwise Simulation of Heat Exchanger Performance - 01 January 1992

STP23790S: Fire Engulfment of Pressure-Liquefied Gas Tanks: Experiments and Modeling - 01 January 1992

STP23795S: Application of Fire and Explosion Risk Assessment to an LPG Bulk Storage Facility - 01 January 1992

STP24686S: Computer Simulation of Stress Corrosion Cracking Behavior of Reactor Pressure Vessel (RPV) Steels in Light Water Reactor (LWR) Environments in Slow Strain Rate Tests (SSRT) - 01 January 1992

STP25828S: Fretting Fatigue in the Power Generation Industry: Experiments, Analysis, and Integrity Assessment - 01 January 1992

STP25835S: Improving Fretting Fatigue Strength at Elevated Temperatures by Shot Peening in Steam Turbine Steel - 01 January 1992

STP25837S: The Fretting Fatigue Properties of a Blade Steel in Air and Vapor Environments - 01 January 1992

STP25840S: ACSR Electrical Conductor Fretting Fatigue at Spacer Clamps - 01 January 1992

STP19094S: Detectability of Defects in Reactor Pressure Components by Location and Interpretation of AE-Sources - 01 January 1991

STP19102S: Cavitation Monitoring of Hydroturbines with RMS Acoustic Emission Measurement - 01 January 1991

STP17609S: Monitoring Water Quality in Thermal Power Systems - 01 January 1991

STP17287S: Power Plant Water Chemistry Research at EPRI in the 1990's - 01 January 1991

STP17289S: Nuclear Power Plant Water Quality in the 1990s -- An INPO Perspective - 01 January 1991

STP17290S: Long-Term Management of Hanford Site Single-Shell Tank Waste - 01 January 1991

STP16858S: Observations in Conducting J-R Curve Tests on Nuclear Piping Materials - 01 January 1991

STP1132-EB: Zirconium in the Nuclear Industry: Ninth International Symposium - 01 January 1991

STP25503S: Effect of Tensile Deformation on Crystallographic Texture in Zircaloy Sheet - 01 January 1991

STP25504S: Correlation of Microstructure and Mechanical Properties of Zr-Sn Alloys - 01 January 1991

STP25506S: Microstructure of Zr-2.5Nb Alloy Pressure Tubing - 01 January 1991

STP25507S: Growth in Zircaloy-4 Fuel Clad Arising from Oxidation at Temperatures in the Range 623 to 723 K - 01 January 1991

STP25508S: Effects of Recrystallization and Neutron Irradiation on Creep Anisotropy of Zircaloy Cladding - 01 January 1991

STP25509S: The Contribution of Irradiation Growth to Pressure Tube Deformation - 01 January 1991

STP25510S: Fatigue Behavior of Neutron Irradiated Zircaloy-2 Fuel Cladding Tubes - 01 January 1991

STP25511S: Fracture Toughness of Irradiated Zr-2.5Nb Pressure Tubes from CANDU Reactors - 01 January 1991

STP25512S: Controlled Composition Zircaloy-2 Uniform Corrosion Resistance - 01 January 1991

STP25513S: Influence of Alloy Composition and Processing on the Nodular Corrosion Resistance of Zircaloy-2 - 01 January 1991

STP25515S: Investigation of Nodular Corrosion Mechanism for Zircaloy Products - 01 January 1991

STP25517S: Development of Highly Corrosion Resistant Zirconium-Base Alloys - 01 January 1991

STP25497S: Deformability of Zirconium-Lined Cladding Tube in Cold Pilgering - 01 January 1991

STP25518S: Effect of Alloying Elements on Uniform Corrosion Resistance of Zirconium-based Alloys in 360°C Water and 400°C Steam - 01 January 1991

STP25519S: Oxide Growth Mechanism on Zirconium Alloys - 01 January 1991

STP25496S: Zirconium-Alloy Corrosion: A Review Based on an International Atomic Energy Agency (IAEA) Meeting - 01 January 1991

STP25520S: Raman Spectroscopy Study of the Tetragonal-to-monoclinic Transition in Zirconium Oxide Scales and Determination of Overall Oxygen Diffusion by Nuclear Microanalysis of O18 - 01 January 1991

STP25521S: Effect of Alloying Elements in Zircaloy on Photo-Electrochemical Characteristics of Zirconium Oxide Films - 01 January 1991

STP25522S: Microanalysis of the Matrix and the Oxide-Metal Interface of Uniformly Corroded Zircaloy - 01 January 1991

STP25523S: Precipitate Behavior in Zircaloy-2 Oxide Films and Its Relevance to Corrosion Resistance - 01 January 1991

STP25498S: Processing Map and Hot Working Characteristics of Zircaloy-2 - 01 January 1991

STP25525S: Corrosion-Electrochemical Properties of Zirconium Intermetallics - 01 January 1991

STP25526S: Comparison of Zircaloy Corrosion Models from the Evaluation of In-Reactor and Out-of-Pile Loop Performance - 01 January 1991

STP25527S: Enhancement of Aqueous Corrosion of Zircaloy-4 Due to Hydride Precipitation at the Metal-Oxide Interface - 01 January 1991

STP25529S: Corrosion of Zircaloy in the Presence of LiOH - 01 January 1991

STP25531S: Lithium Uptake and the Corrosion of Zirconium Alloys in Aqueous Lithium Hydroxide Solutions - 01 January 1991

STP25532S: Corrosion of Zircaloy-4 Pwr Fuel Cladding in Lithiated and Borated Water Environments - 01 January 1991

STP25499S: Establishing Statistical Models of Manufacturing Parameters: Zircaloy-4 Cladding Tube Properties - 01 January 1991

STP25533S: Effects Of LiOH on Pretransition Zirconium Oxide Films - 01 January 1991

STP25534S: Investigation of Variables That Influence Corrosion of Zirconium Alloys during Irradiation - 01 January 1991

STP25535S: Characteristics of Autoclave and In-Reactor Nodular Corrosion of Zircaloys - 01 January 1991

STP25536S: Amorphization of Precipitates in Zircaloy under Neutron and Charged-Particle Irradiation - 01 January 1991

STP25537S: Oxide Characteristics and Their Relationship to Hydrogen Uptake in Zirconium Alloys - 01 January 1991

STP25538S: The Corrosion of Zircaloy-4 Fuel Cladding in Pressurized Water Reactors - 01 January 1991

STP25500S: Texture Control in Zircaloy Tubing Through Processing - 01 January 1991

STP25501S: Fracture Toughness Evaluation of Heat-Treated Zr-2.5Nb Pressure Tubes - 01 January 1991

STP24635S: Effects of Thermal Aging on Precipitate Development of Alloy Ht-9 - 01 January 1990

STP1046-EB: Effects of Radiation on Materials: 14th International Symposium (Volume I) - 01 January 1990

STP24636S: Swelling Suppression in Phosphorus-Modified Fe-Cr-Ni Alloys During Neutron Irradiation - 01 January 1990

STP24637S: Microstructural Evolution of Neutron Irradiated Fe-Cr-Ni Alloys at 495°C in Response to Changes in the Helium/DPA Ratio - 01 January 1990

STP24638S: Microstructural Development of Titanium-Modified Austenitic Stainless Steel Under Neutron Irradiation in HFIR up to 57 dpa - 01 January 1990

STP24639S: The Microstructural Evolution and Swelling Behavior of Type 316 Stainless Steel Irradiated in HFIR - 01 January 1990

STP24640S: Swelling Resistance of the Highly Deformed Titanium-Modified Austenitic Stainless Steel - 01 January 1990

STP24641S: Variations of Phase and Structure in Austenitic Stainless Steel Under Heavy Ion Irradiation - 01 January 1990

STP24642S: Ion Bombardment Radiation Damage Studies of Fusion-Relevant Austenitic and Ferritic Alloys - 01 January 1990

STP24643S: High Temperature Helium Embrittlement: Austenitic Versus Martensitic Stainless Steels - 01 January 1990

STP24644S: Helium Effects on Neutron-Irradiated Cr-Mo Ferritic Steels: A Review of Recent Results - 01 January 1990

STP24645S: Microhardness—Microstructure Study of Aged Nimonic 90 Irradiated with Helium - 01 January 1990

STP24646S: High Temperature Embrittlement of Hastelloy X After Low Fluence Neutron Irradiation—An Effect of Helium? - 01 January 1990

STP24647S: On the Role of Helium in High Temperature Embrittlement of Irradiated Austenitic Steels - 01 January 1990

STP24648S: Effects of Irradiation on Grain Boundary Deformation in Nickel - 01 January 1990

STP24649S: Helium-Induced Degradation in the Weldability of an Austenitic Stainless Steel - 01 January 1990

STP24650S: Isotopically Alloyed Injector Foils for Helium Effects Research in Mixed-Spectrum Reactors - 01 January 1990

STP24651S: The Growth of Bubbles in Pure Aluminum During and After Irradiation with 600 MeV Protons - 01 January 1990

STP24652S: Cavitation and Embrittlement in Tritium Exposed Copper - 01 January 1990

STP24653S: Modeling Studies on the Precipitation of Krypton After Implantation into Metals - 01 January 1990

STP24631S: Void Formation and Helium Effects in 9Cr-1MoVNb and 12Cr-1MoVW Steels Irradiated in HFIR and FFTF at 400°C - 01 January 1990

STP24654S: Simulation of Solid Inert Gas Bubbles in Metals - 01 January 1990

STP24655S: Radiation-Induced Segregation of Phosphorus in Nickel and Fe-Cr-Ni Alloys - 01 January 1990

STP24656S: Characteristics of Radiation-Induced Solute Segregation in Candidate and Model Ferritic Alloys - 01 January 1990

STP24657S: Segregation to Surfaces in Irradiated Stainless Steels - 01 January 1990

STP24658S: Irradiation-Assisted Stress Corrosion Cracking and Grain Boundary Segregation in Heat Treated Type 304 SS - 01 January 1990

STP24659S: Irradiation-Induced Solid Solution Decomposition Enhances Point Defect Recombination - 01 January 1990

STP24660S: Microstructural Development in Neutron Irradiated Zircaloy-4 - 01 January 1990

STP24661S: Electron Irradiation-Induced Amorphization of Precipitates in Zircaloy-2 - 01 January 1990

STP24662S: The Influence of Microstructure and Solutes on Void Formation and Void Growth in Irradiated Materials - 01 January 1990

STP24663S: The Stochastic Instability of a Spatially Homogeneous Void Distribution in Irradiated Metals: The Distribution Function Approach - 01 January 1990

STP24664S: The Leading Factor Transient Regime of Void Swelling: The Role of Bias Vacancy Flow Around Growing Precipitates - 01 January 1990

STP24665S: The Development of Periodical Spatial Structures in Crystals under Irradiation - 01 January 1990

STP24666S: Surface effect on Dislocation Loop Formation - 01 January 1990

STP24667S: The Slowing Down of Dislocation Climb by Voids at Later Stages of Material Irradiation - 01 January 1990

STP24668S: Influence of Small Bubble Sink Strength on the Swelling Rate of Voids in Austenitic Stainless Steel AISI 316 L - 01 January 1990

STP24669S: Nucleation of Helium Bubbles at Grain Boundaries During Irradiation - 01 January 1990

STP24670S: Void Ensemble Response to Periodical Variations of Irradiation Conditions - 01 January 1990

STP24671S: An HVEM Study of Displacement Cascade Damage in Nb3Sn at 13 K - 01 January 1990

STP24672S: A Study of Cascade Cluster Formation and Interaction in Ion-Irradiated Gold by In-Situ Observation - 01 January 1990

STP24630S: Behavior and Microstructure of Ferritic Steels Irradiated in the Phénix Reactor - 01 January 1990

STP24673S: The Production Rate of Freely Migrating Defects in Self-Ion Irradiated Nickel and Fe-Cr-Ni Alloys - 01 January 1990

STP24632S: Microstructural Change in Ferritic Steels Under Heavy Ion Irradiation - 01 January 1990

STP24674S: Alternative Polarity Recombination Centers of Point Defects - 01 January 1990

STP24675S: Estimation of Radiation Vacancy Rate Absorption by Grain Boundaries - 01 January 1990

STP24676S: Helium Bubbles in Copper Studied by Positron Annihilation - 01 January 1990

STP24677S: Study of Helium Diffusion to Grain Boundaries by the Method of Internal Friction - 01 January 1990

STP24678S: Phase Dissolution Caused by Reimplantation Studied by Mössbauer Effect - 01 January 1990

STP24679S: Effect of Electron and Gamma-Ray Irradiation on the Chemical Composition and Atomic Distribution of Copper- and Iron-Based Alloys - 01 January 1990

STP24633S: Neutron Irradiation Damage in Ferrltic Fe-Cr Alloys - 01 January 1990

STP24634S: Influence of Structure and Phase Composition on 1Cr13Mo2NbVB Steel Mechanical Properties in Initial, Aged, and Irradiated States - 01 January 1990

STP24952S: Decrease of Ductility Due to Hydrogen in Fe-Cr-Mn Steel - 01 January 1990

STP1047-EB: Reduced Activation Materials for Fusion Reactors - 01 January 1990

STP24953S: Effects of Irradiation on Low Activation Ferritic Alloys: A Review - 01 January 1990

STP24954S: Optimization of Reduced Activation Ferritic Steels - 01 January 1990

STP24955S: Low Chromium Reduced-Activation Ferritic Steels - 01 January 1990

STP24956S: The Post-Irradiation Tensile Properties and Microstructure of Several Vanadium Alloys - 01 January 1990

STP24957S: A TEM Study of V and V-lat.%10B with Fast Neutron Irradiations - 01 January 1990

STP24958S: Microstructure of Neutron Irradiated Vanadium Alloys - 01 January 1990

STP24959S: Defect Behavior and Microstructural Evolution in Vanadium-Base Alloys Under Irradiation in a High-Voltage Electron Microscope - 01 January 1990

STP24946S: An Assessment of Fe-Cr-Mn Austenitic Alloys for Fusion Service Using Fast Reactor Irradiation - 01 January 1990

STP24960S: EB Welding of Low-Activation Vanadium-Binary Alloys - 01 January 1990

STP24961S: Diffusion Bonding Between Vanadium and Alumina - 01 January 1990

STP24962S: Solid State Reactions Between V-Base Alloys and Silicon Carbide at High Temperatures - 01 January 1990

STP24947S: Design of Low Activation Austenitic Steels by the d-Electron Concept - 01 January 1990

STP24948S: Irradiation Effects on Mechanical Properties of High Manganese Steels - 01 January 1990

STP24949S: Precipitation Sensitivity to Alloy Composition in Fe-Cr-Mn Austenitic Steels Developed for Reduced Activation for Fusion Application - 01 January 1990

STP24945S: Reduced Activation Austenitic Stainless Steels: The Fe-Mn-Cr-C System - 01 January 1990

STP24950S: The Dependence of ☌-Phase Formation in Fe-Cr-Mn Alloys on Cold Work, Aging, and Alloy Composition - 01 January 1990

STP24951S: The Effect of Composition and Phase on Segregation of Fe-Cr Based Alloys - 01 January 1990

STP24065S: Environmental Acceleration of Fatigue Crack Growth in Reactor Pressure Vessel Materials and Environments - 01 January 1990

STP24071S: Modeling of Sulfide Inclusion Distributions in Relation to the Environmentally Assisted Cracking of Low-Alloy Steels in a Pressurized Water Reactor Environment - 01 January 1990

STP24081S: Fatigue Crack Growth Behavior of Different Stainless Steels in Pressurized Water Reactor Environments - 01 January 1990

STP24082S: Environmentally Assisted Cracking Behavior of a High-Level Nuclear Waste Container Alloy - 01 January 1990

STP26066S: Accepting Risk: Responsibility Versus Liability - 01 January 1990

STP18969S: Development and Evaluation of Analytical Techniques for Total Chlorine in Used Oils and Oil Fuels - 01 January 1990

STP25303S: Engineering and Compaction Characteristics of Boiler Slag - 01 January 1990

STP18999S: Effects of Warm Pre-Stressing on the Transition Toughness Behavior of an A533 Grade B Class 1 Pressure Vessel Steel - 01 January 1990

STP19003S: Effect of Dynamic Strain Aging on Fracture Resistance of Carbon Steels Operating at Light-Water Reactor Temperatures - 01 January 1990

STP23536S: Fractographic Study of Isolated Cleavage Regions in Nuclear Pressure Vessel Steels and Their Weld Metals - 01 January 1990

STP10066S: Surveillance Neutron Dosimetry at the Hungarian Nuclear Power Plant - 01 January 1989

STP1001-EB: Reactor Dosimetry: Methods, Applications, and Standardization - 01 January 1989

STP10067S: Analysis of First Pressure Vessel Surveillance Capsule from Kršsko Nuclear Power Plant - 01 January 1989

STP10068S: Experimental and Theoretical Neutron Flux Estimations at the Surveillance Chain, at the Pressure Vessel Inner Surface, and in the Cavity of a WER-440 PWR - 01 January 1989

STP10057S: Reactor Dosimetry and Nuclear Reactor Regulation - 01 January 1989

STP10069S: Experimental Validation of Neutron Calculations for WWER Pressure Vessel Neutron Exposure Evaluation - 01 January 1989

STP10070S: Pressure Vessel Neutron Dosimetry at Three Pressurized Water Reactor Plants Using Niobium Monitors - 01 January 1989

STP10071S: Application of Ex-Vessel Neutron Dosimetry for Determination of Vessel Fluence - 01 January 1989

STP10072S: Description of the Babcock & Wilcox Owners Group Cavity Dosimetry Benchmark Experiment - 01 January 1989

STP10073S: Neutron Exposure of Gundremmingen-A Pressure Vessel Trepans - 01 January 1989

STP10074S: Solid-State Track Recorder Pressure Vessel Surveillance Neutron Dosimetry at Commercial Light Water Reactors - 01 January 1989

STP10058S: Improvement of LWR Pressure Vessel Steel Embrittlement Surveillance: 1984–1986 Progress Report on Belgian Activities in Cooperation with USNRC and Other R&D Programs - 01 January 1989

STP10075S: Transport Calculation of the Gamma Field in the Ex-Core Region of the KrŠko Pressure Water Reactor - 01 January 1989

STP10076S: Remote Gamma-Ray Mapping: Nuclear Installation Remote Activity Location Device - 01 January 1989

STP10077S: Neutron Sensitivity of LiF Chip Gamma Dosimeters at Megagray Doses - 01 January 1989

STP10078S: High Absorbed Dose (104 to 108 Gy) Gamma Dosimeters Based on Organic Conductors:Tests Performed in the Irradiation Plant of Reactor Osiris - 01 January 1989

STP10079S: Nuclear Data for the Use of Niobium as Neutron Fluence Monitor - 01 January 1989

STP10080S: Measurement of the 93Nb(n,n′) Fission Spectrum Cross Section - 01 January 1989

STP10081S: Measurements of Fission Spectrum Averaged Cross Sections for the 93Nb(n,n′)93mNb Reaction - 01 January 1989

STP10082S: Measurement of 93mNb for Fast Neutron Metrology - 01 January 1989

STP10083S: Development of the Be(d,n) Neutron Source for Cross-Section Investigations in the Few-MeV Energy Range - 01 January 1989

STP10084S: Nuclear Data Problems Encountered in Reactor Neutron Metrology - 01 January 1989

STP10085S: A Review of Photofission Measurements - 01 January 1989

STP10086S: Integral Test of Cross Sections for 54Fe(n,p)54Mn Reaction in JENDL-3T - 01 January 1989

STP10087S: Power Reactor Neutron Dosimetry: Experimental Estimate of the Influences Due to Local Changes in Core Configuration and Gamma-Induced Reactions - 01 January 1989

STP10088S: Review of the NESTOR Shielding and Dosimetry Improvement Programme (NESDIP) - 01 January 1989

STP10089S: Power Reactor Benchmark Studies - 01 January 1989

STP10090S: Diffusion Theory Calculations for the Pin-Wise Power Distribution in VENUS-I and VENUS-II - 01 January 1989

STP10091S: Light-Water Reactor Radial Shield Benchmark Studies of the NESTOR Shielding and Dosimetry Improvement Programme (NESDIP) - 01 January 1989

STP10092S: Neutron Spectrum Measurements in SEG-V Benchmark System - 01 January 1989

STP10093S: Status of Cf-252 Neutron Spectrum as a Standard - 01 January 1989

STP10094S: Nuclear Research Emulsion Measurements and the Observation of Proportional Counter Perturbation Factors in VENUS-1 - 01 January 1989

STP10095S: Calibration Problems in the Direct Measurement of Radiation Absorbed Dose - 01 January 1989

STP10096S: Neutronic Study of a PAHR Irradiation Experiment in BR2 - 01 January 1989

STP10097S: Results of a Neutron Flux Perturbation Experiment with Babcock & Wilcox Owners Group Surveillance Capsules - 01 January 1989

STP10098S: Determination of Neutron Exposure in the Buffalo Reactor - 01 January 1989

STP10059S: Reactor Dosimetry: Standardization of Procedures and Considerations on Further Development for LWR PV Surveillance in the Federal Republic of Germany - 01 January 1989

STP10099S: A Contribution to the Theory of Reactor Pressure Vessel Dosimetry - 01 January 1989

STP10100S: Application of LEPRICON Methodology to LWR Pressure Vessel Surveillance Dosimetry - 01 January 1989

STP10101S: On the Problems Encountered in Activation Spectrometry and Subsequent Radiation Damage Predictions - 01 January 1989

STP10102S: Unfolding and Radiation Damage Prediction with and without a priori Information - 01 January 1989

STP10103S: Role of Covariances in Reactor Dosimetry - 01 January 1989

STP10104S: Experience In the Design of Irradiation Rigs for the Harwell D20 Moderated Materials Testing Reactors - 01 January 1989

STP10060S: The Light Water Reactor Pressure Vessel Surveillance Dosimetry Improvement Program (LWR-PV-SDIP): Past Accomplishments, Recent Developments, and Future Directions - 01 January 1989

STP10105S: Derivation of Neutron Exposure Parameters from Threshold Detector Measurements - 01 January 1989

STP10106S: Neutron Spectrum Adjustment with SANDII Using Arbitrary Trial Functions - 01 January 1989

STP10107S: High Energy Neutron Dosimetry (European Survey) - 01 January 1989

STP10108S: The U.S. Fusion Materials Program: Status and Directions - 01 January 1989

STP10109S: High Energy Neutron Dosimetry of a Spallation Neutron Source - 01 January 1989

STP10110S: Dosimetry for a Radiation Damage Experiment in a Spallation Neutron Source - 01 January 1989

STP10111S: Measurement of Long-Lived Radionuclides in Fusion Materials - 01 January 1989

STP10112S: Helium Production in Mixed-Spectrum Fission Reactors - 01 January 1989

STP10113S: Observation of Pulsed Neutron Fields with Solid-State Track Recorders - 01 January 1989

STP10114S: Status Report on NRC/MEA Dose Rate Experiments in the Buffalo Reactor - 01 January 1989

STP10115S: European Workshop on Radiation Damage Correlations and Dosimetry - 01 January 1989

STP10116S: Design and Use of the Embrittlement Data Base (EDB) - 01 January 1989

STP10117S: Détermination de fonctions de dommages pour les matériaux polyatomiques irradiées en réacteurs de recherche - 01 January 1989

STP10118S: Determination of Damage Functions for Polyatomic Materials Irradiated in Research Reactors - 01 January 1989

STP10119S: Evaluation of Radiation-Damage Cross Sections for (Homogeneous) Amorphous Structure Materials - 01 January 1989

STP10120S: SPECOMP Calculations of Radiation Damage in Compounds - 01 January 1989

STP10121S: Determination of Gamma-Ray-Induced Displacement Rates - 01 January 1989

STP10122S: Constant Chemistry Analysis (CCA) Approach to Predicting Transition Temperature Shift in Pressure Vessel Steels under Neutron Irradiation - 01 January 1989

STP10123S: Neutron Dosimetry Materials Used in European Community Countries - 01 January 1989

STP10061S: Récente amélioration en dosimétrie de surveillance des cuves dans les réacteurs en construction de l'Electricité de France - 01 January 1989

STP10124S: Fast Neutron Dosimetry by Means of Fission Foils - 01 January 1989

STP10125S: Application of Boron Covers for Neutron Spectrum Determination Purposes in Various Neutron Environments - 01 January 1989

STP10126S: Intercomparison of Activity Measurements in Different Laboratories on a Set of Monitor Foils Irradiated in a Spallation Neutron Spectrum - 01 January 1989

STP10127S: Use of Sapphire as a Neutron Damage Monitor for Pressure Vessel Steels - 01 January 1989

STP10128S: Correction of Burn-In Effects in Fission Neutron Dosimeters - 01 January 1989

STP10129S: Analysis of Solid-State Track Recorders with the Westinghouse Research and Development Center Automated Track Counter - 01 January 1989

STP10130S: Preparation of Ultra High Purity Niobium for Monitoring Neutron Fluence - 01 January 1989

STP10131S: Spectrum Measurements on Filtered Neutron Beams for Medical Applications - 01 January 1989

STP10132S: Analysis of Neutron Emission on PWR Spent Fuel Assemblies for Burn-Up Assessment - 01 January 1989

STP10062S: Recent Improvement in Vessel Surveillance Dosimetry for the Electricité de France Reactors under Construction - 01 January 1989

STP10133S: Self-Powered Neutron Detectors for Measuring Epithermal Neutron Flux - 01 January 1989

STP10134S: Neutron Sensitivity of Prompt-Response Self-Powered Neutron Detectors and the Interval Rule - 01 January 1989

STP10135S: Electron Spectral Contribution of Prompt-Response Self-Powered Neutron Detectors - 01 January 1989

STP10136S: Measurements and Model Predictions for Improved Microcalorimeter Design - 01 January 1989

STP10137S: Calibration of a Neutron-Driven Gamma-Ray Source - 01 January 1989

STP10138S: Personnel Neutron Dosimetry Area Monitoring Using Solid-State Track Recorders - 01 January 1989

STP10056S: Impact of USA-Euratom Cooperative Dosimetry Research on NRC Regulation of Light Water Reactors - 01 January 1989

STP10063S: U.S. Utility's Experience with Surveillance Dosimetry - 01 January 1989

STP10064S: Interactions Between Fluence Variations and Material Properties Data for Large Surveillance Capsules - 01 January 1989

STP10065S: Nuclear Plant Life Extension - 01 January 1989

STP1011-EB: Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Third Volume) - 01 January 1989

STP10390S: Irradiation Programs to Establish the Safety Margins of German Licensing Rules Related to RPV Steel Embrittlement - 01 January 1989

STP10391S: Development of Reactor Pressure Vessel Design, Neutron Fluence Calculation, and Material Specification to Minimize Irradiation Effects - 01 January 1989

STP10392S: Effectiveness of Flux Reduction Measures Instituted at the Maine Yankee Atomic Power Station - 01 January 1989

STP10393S: Residual Life Assessment of Light Water Reactor Pressure Vessels - 01 January 1989

STP10394S: Radiation Embrittlement Trend Curves and the Impact on Nuclear Plant Operating Criteria - 01 January 1989

STP10395S: Evaluation of Thermal Annealing Behavior of Neutron-Irradiated Reactor Pressure Vessel Steels Using Nondestructive Test Methods - 01 January 1989

STP10396S: Semiempirical Model for Annealing and Reirradiation Embrittlement in Pressure Vessel Steels - 01 January 1989

STP10397S: Status of Research to Assess Radiation Effects on Crack-Arrest Toughness of RPV Steels - 01 January 1989

STP10398S: Defect Particles in an Irradiated RPV Steel Studied by a Systematic Variation of Irradiation and Annealing Conditions: Preliminary Results by Small Angle Neutron Scattering - 01 January 1989

STP10399S: SANS Investigation of Irradiated A533-B Steels Doped with Phosphorus - 01 January 1989

STP10400S: Positron Lifetime Characterization of Irradiated Pressure Vessel Model Alloys - 01 January 1989

STP10384S: Overview of U.S. Research and Regulatory Activities on Neutron Radiation Embrittlement of Pressure Vessel Steel - 01 January 1989

STP10385S: Studies in the United Kingdom on Neutron Irradiation Embrittlement of Pressure Vessel Steels - 01 January 1989

STP10383S: Assurance of the Pressure Vessel Integrity with Respect to Irradiation Embrittlement: Activities in the Federal Republic of Germany - 01 January 1989

STP10386S: The Swiss Research Program on Irradiation Embrittlement and Annealing of Reactor Pressure Vessel Steels - 01 January 1989

STP10387S: Evaluation of WWER-440 Surveillance at Paks NPS - 01 January 1989

STP10388S: Neutron Embrittlement Surveillance Program at Krṡko Nuclear Power Plant - 01 January 1989

STP10389S: Characteristics of the IAEA Correlation Monitor Material for Surveillance Programs - 01 January 1989

STP19711S: Soil Characteristics as Criteria for Cathodic Protection of a Nuclear Fuel Production Facility - 01 January 1989

STP18687S: A Turbine Lube Oil System Monitoring Program - 01 January 1989

STP1021-EB: Turbine Oil Monitoring - 01 January 1989

STP18688S: A Supplier's Approach to Turbine Oil Monitoring - 01 January 1989

STP18689S: The Reliable Control of Oil Quality in Japanese Turbine Units - 01 January 1989

STP18686S: Background and Development of ASTM D 4378: Practice for In-Service Monitoring of Mineral Turbine Oils for Steam and Gas Turbines - 01 January 1989

STP18690S: Monitoring Practices for Phosphate Ester Fluids for Turbine Lubrication and Control - 01 January 1989

STP18860S: Influence of Chemical Composition on Uniform Corrosion of Zirconium-Base Alloys in Autoclave Tests - 01 January 1989

STP1023-EB: Zirconium in the Nuclear Industry: Eighth International Symposium - 01 January 1989

STP18861S: Correlation Between 400°C Steam Corrosion Behavior, Heat Treatment, and Microstructure of Zircaloy-4 Tubing - 01 January 1989

STP18862S: Influence of the Manufacturing Process on the Corrosion Resistance of Zircaloy-4 Cladding - 01 January 1989

STP18863S: A Laboratory Method to Predict Hydriding Properties of Zirconium Alloys Under Irradiation - 01 January 1989

STP18864S: Development of a Mechanistic Model to Assess the External Corrosion of the Zircaloy Claddings in PWRs - 01 January 1989

STP18865S: Lithium Uptake and the Accelerated Corrosion of Zirconium Alloys - 01 January 1989

STP18866S: Microstructure and Corrosion Studies for Optimized PWR and BWR Zircaloy Cladding - 01 January 1989

STP18855S: Oxidation and Deuterium Uptake of Zr-2.5Nb Pressure Tubes in CANDU-PHW Reactors - 01 January 1989

STP18867S: Corrosion Performance of Zircaloy-2 and Zircaloy-4 PWR Fuel Cladding - 01 January 1989

STP18868S: Development of a Cladding Alloy for High Burnup - 01 January 1989

STP18869S: Enhanced Low-Temperature Oxidation of Zirconium Alloys Under Irradiation - 01 January 1989

STP18870S: Internal Hydriding in Irradiated Defected Zircaloy Fuel Rods - 01 January 1989

STP18871S: A Systematic Survey of the Factors Affecting Zircaloy Nodular Corrosion - 01 January 1989

STP18872S: Corrosion Performance Ranking of Zircaloy-2 for BWR Applications - 01 January 1989

STP18873S: Influence of Chemical Composition and Manufacturing Variables on Autoclave Corrosion of the Zircaloys - 01 January 1989

STP18874S: Effects of Alloying Element Distribution on the Nodular Corrosion of Zircaloy-2 - 01 January 1989

STP18856S: Evaluation of Zircaloy-2 Pressure Tubes from NPD - 01 January 1989

STP18875S: Electron Microscopy Study of Oxide Films Formed on Zircaloy-2 in Superheated Steam - 01 January 1989

STP18876S: Heterogeneous Scale Growth During Steam Corrosion of Zircaloy-4 and 500°C - 01 January 1989

STP18877S: Automatic System for Measuring the Zirconium Liner and Zircaloy-2 Thickness of Zirconium Liner Tubes - 01 January 1989

STP18854S: Corrosion and Hydriding of N Reactor Pressure Tubes - 01 January 1989

STP18878S: Solubility Limits and Formation of Intermetallic Precipitates in ZrSnFeCr Alloys - 01 January 1989

STP18879S: Direct Measurement of Matrix Composition in Zircaloy-4 by Atom Probe Microanalysis - 01 January 1989

STP18880S: Diffusion of 3D Transition Elements in α-Zr and Zirconium Alloys - 01 January 1989

STP18881S: Beta-Quenched Zircaloy-4: Effects of Thermal Aging and Neutron Irradiation - 01 January 1989

STP18882S: Intermetallic Precipitates in Zirconium-Niobium Alloys - 01 January 1989

STP18883S: Magnetic Study of Zircaloy - 01 January 1989

STP18884S: Oxidation Kinetics and Auger Microprobe Analysis of Some Oxidized Zirconium Alloys - 01 January 1989

STP18857S: Growth, Fracture, and Nondestructive Evaluation of Hydride Blisters in Zr-2.5 Nb Pressure Tubes - 01 January 1989

STP18885S: Simulated Fuel Expansion Testing of Zircaloy Tubing - 01 January 1989

STP18886S: Link Between Stress Corrosion and Corrosion-Fatigue Behavior of Zircaloy in an Iodine Environment - 01 January 1989

STP18887S: Effects of Irradiation and Hydriding on the Mechanical Properties of Zircaloy-4 at High Fluence - 01 January 1989

STP18888S: Applications of Crystallographic Textures of Zirconium Alloys in the Nuclear Industry - 01 January 1989

STP18889S: Stress Versus Strain Rate Characteristics of Zircaloy Cladding Tubes Subjected to Various Deformation Paths - 01 January 1989

STP18890S: The Influence of Tin Content on the Thermal Creep of Zircaloy-4 - 01 January 1989

STP18891S: Effects of High Neutron Fluences on Microstructure and Growth of Zircaloy-4 - 01 January 1989

STP18892S: Accelerated Irradiation Growth of Zirconium Alloys - 01 January 1989

STP18858S: Effects of Hydride Morphology on Zr-2.5Nb Fracture Toughness - 01 January 1989

STP18893S: Creep Behavior of Zircaloy Cladding Under Variable Conditions - 01 January 1989

STP18894S: Effects of Microstructural Factors on Irradiation Growth in Zirconium-Niobium Alloys - 01 January 1989

STP18895S: The Effect of Temperature on the Irradiation Growth of Cold-Worked Zr-2.5 Nb - 01 January 1989

STP18859S: Effects of Loading and Thermal Maneuvers on Delayed Hydride Cracking in Zr-2.5 Nb Alloys - 01 January 1989

STP24576S: The Effects of Phosphorus and Boron on the Behavior of a Titanium Stabilized Austenitic Stainless Steel Developed for Fast Reactor Service - 01 January 1989

STP17175S: Increased Pressure Vessel Fatigue Life Caused by Decreased Autofrettage - 01 January 1988

STP10051S: Fuel Quality Program for Long-Term Storage of Gas Turbine Distillate Fuel in Large Tanks - 01 January 1988

STP24478S: Cyclic Stress-Strain-Time Response of a 9Cr-1Mo-V-Nb Pressure Vessel Steel at High Temperature - 01 January 1988

STP24549S: Low Cycle Fatigue Characterization of a HP-IP Steam Turbine Rotor - 01 January 1988

STP24535S: Fatigue Life and Short Crack Propagation of Turbine Rotor Steels under Variable Strain Loading - 01 January 1988

STP23245S: Propagating Shear Fracture in Natural Gas Transmission Pipelines - 01 January 1988

STP23256S: Determination of the Fracture Toughness of Irradiated Reactor Pressure Tubes Using Curved Compact Specimens - 01 January 1988

STP23272S: Application of Direct Measurement of J-Integral on a Pressure Vessel with Axial Notch - 01 January 1988

STP966-EB: Deformation Mechanisms, Texture, and Anisotropy in Zirconium and Zircaloy - 01 January 1988

STP25976S: Estimation of Reservoir Submerging Losses Using CIR Aerial Photographs: Example of the Ertan Hydropower Station on the Yalong River in Southwest China - 01 January 1988

STP33077S: Role of Damage Tolerance and Fatigue Crack Growth in the Power Generation Industry - 01 January 1988

STP33085S: Effect of Temperature and Strain Rate on Upper Shelf Fracture Behavior of A533B Class 1 Pressure Vessel Steel - 01 January 1988

STP33094S: A Cooperative Study for the Evaluation of Crack Arrest Toughness of RPV Materials in Japan - 01 January 1988

STP33104S: Review of Pressurized-Water-Reactor-Related Thermal Shock Studies - 01 January 1988

STP33105S: Pressurized Thermal Shock Experiments with Thick Vessels - 01 January 1988

STP33109S: Fatigue Crack Growth Rate Properties of SA508 and SA533 Pressure Vessel Steels and Submerged-Arc Weldments in a Pressurized Water Environment - 01 January 1988

STP26148S: Viscoelastic/Damage Modeling of Filament-Wound Cylindrical Pressure Vessels - 01 January 1988

STP26207S: Galvanic Corrosion in Power Plant Condensers - 01 January 1988

STP26208S: Experience with Cathodic Protection of Power Plant Condensers Operating with High Performance Ferritic Stainless Steel Tubing - 01 January 1988

STP29123S: Development of Microstructure to Optimize Mechanical Performance of Power Generation Equipment - 01 January 1988

STP29125S: New Low Chromium Ferritic Pressure Vessel Steels - 01 January 1988

STP26318S: An Improved Air-Supplied Plastic Suit for Protection Against Tritium - 01 January 1988

STP26359S: Measurements of the Reduction Due to Proof Loads of Residual Stresses in Simulated Pressure Vessel Welds - 01 January 1988

STP27722S: A Study of the Initiation and Growth of Complex Cracks in Nuclear Piping Under Pure Bending - 01 January 1988

STP27723S: Elastic-Plastic Assessment of a Cladded Pressurized-Water-Reactor Vessel Strength Since Occurrence of a Postulated Underclad Crack During Manufacturing - 01 January 1988

STP26410S: From Wood to Coal: A Compositional Thermogravimetric Analysis - 01 January 1988

STP26412S: Analysis of Flue Gas Scrubber Materials from a Coal-Fired Power Plant by Thermogravimetry - 01 January 1988

STP26413S: Compositional Analysis of Solid Waste and Refuse Derived Fuels by Thermogravimetry - 01 January 1988

STP26425S: A Review of the Operating Principles and Practice of Dissolved Gas Analysis - 01 January 1988

STP998-EB: Electrical Insulating Oils - 01 January 1988

STP26426S: An Engineering Model for Streaming Electrification in Power Transformers - 01 January 1988

STP26427S: Static Electrification in Power Transformers - 01 January 1988

STP26419S: PCBs: The Beginning, the Muddle, the End? - 01 January 1988

STP26420S: Insulating Oil Qualification and Acceptance Tests from a User's Perspective - 01 January 1988

STP26421S: Significance of Transformer Oil Properties - 01 January 1988

STP26422S: Newly Developed Analytical Techniques for Characterization of Insulating Oils - 01 January 1988

STP26418S: Mineral Insulating Oil Manufacture and Safekeeping - 01 January 1988

STP26423S: Transformer Fault Gas Analysis and Interpretation—A User's Perspective - 01 January 1988

STP26424S: Criteria for the Interpretation of Data for Dissolved Gases in Oil from Transformers (A Review) - 01 January 1988

STP26437S: Round-Robin Study of Leaching Methods as Applied to Solid Wastes from Coal-Fired Power Plants - 01 January 1988

STP26440S: Development of a Portable Testing Procedure for Monitoring Halogenated Solvents in Waste Fuels - 01 January 1988

STP18506S: Performance of a Group of Well-Insulated Solar Houses in the United Kingdom - 01 January 1987

STP24359S: Chapter 3 High Voltage Measurements - 01 January 1987

STP926-EB: Engineering Dielectrics Volume IIB Electrical Properties of Solid Insulating Materials: Measurement Techniques - 01 January 1987

STP24360S: Chapter 4 Surface Failure Measurements - 01 January 1987

STP24361S: Chapter 5 Polymer Degradation and Its Measurement - 01 January 1987

STP24357S: Chapter 1 Direct-Current Conductivity Measurements - 01 January 1987

STP24362S: Chapter 6 Electrostatic Charge Measurements - 01 January 1987

STP24363S: Chapter 7 Statistical Methods for the Evaluation of Electrical Insulating Systems - 01 January 1987

STP24358S: Chapter 2 Alternating-Current Loss and Permittivity Measurements - 01 January 1987

STP24364S: Chapter 8 Systems of Units - 01 January 1987

STP926-EB: Engineering Dielectrics Volume IIB: Electrical Properties of Solid Insulating Materials: Measurement Techniques - 01 January 1987

STP28110S: Effect of Irradiation at 588 K on Mechanical Properties and Deformation Behavior of Zirconium Alloy Strip - 01 January 1987

STP939-EB: Zirconium in the Nuclear Industry - 01 January 1987

STP28111S: Upper and Lower Bound Crystal Plastic Modelling of Creep Loci of Zircaloy - 01 January 1987

STP28113S: Recycling Off-Grade Zircaloy Scrap Using a Molten-Salt Electro-Refining Process - 01 January 1987

STP28114S: Influence of Hydrostatic Extrusion on Properties of Zirconium and Zircaloys - 01 January 1987

STP28116S: Laser Beam Beta Heat Treatment of Zircaloy - 01 January 1987

STP28118S: Long-Term Corrosion and Deuterium Uptake in CANDU-PHW Pressure Tubes - 01 January 1987

STP28120S: Effects of Heat Flux and Irradiation-Induced Changes in Water Chemistry on Zircaloy Nodular Oxidation - 01 January 1987

STP28122S: Prevention of Delayed Hydride Cracking in Zirconium Alloys - 01 January 1987

STP28106S: Anisotropy in Zircaloy - 01 January 1987

STP28123S: Parametric Study of an Autoclave Test for Nodular Corrosion - 01 January 1987

STP28124S: Development of a Sensitive and Reproducible Steam Test for Zircaloy Nodular Corrosion - 01 January 1987

STP28126S: Influence of Impurities and Temperature on the Microstructure of Zircaloy-2 and Zircaloy-4 after the Beta → Alpha Phase Transformation - 01 January 1987

STP28128S: Influence of Second-Phase Particles on Zircaloy Corrosion in BWR Environment - 01 January 1987

STP28130S: Nucleation and Growth of Intermetallic Precipitates in Zircaloy-2 and Zircaloy-4 and Correlation to Nodular Corrosion Behavior - 01 January 1987

STP28131S: Nodular Corrosion Resistance of Zircaloy-2 in Relation to Second-Phase Particle Distribution - 01 January 1987

STP28132S: Effect of Beta Quenching on the Microstructure and Corrosion of Zircaloys - 01 January 1987

STP28107S: Zirconium Activities in Europe: 1945–1984 - 01 January 1987

STP28133S: Effect of Chemistry on Elevated Temperature Nodular Corrosion - 01 January 1987

STP28134S: Mechanistic Studies of Zircaloy Nodular Corrosion - 01 January 1987

STP28135S: Progress in the Knowledge of Nodular Corrosion - 01 January 1987

STP28136S: Influence of Variations in Early Fabrication Steps on Corrosion, Mechanical Properties, and Structure of Zircaloy-4 Products - 01 January 1987

STP28138S: Zircaloy Fuel Cladding Behavior in a Loss-of-Coolant Accident: A Review - 01 January 1987

STP28139S: Oxidation of Zircaloy-4 in Steam at 1300 to 2400°C - 01 January 1987

STP28108S: An Overview of Microstructural and Experimental Factors That Affect the Irradiation Growth Behavior of Zirconium Alloys - 01 January 1987

STP28141S: Experimental and Theoretical Results of Cladding Oxidation Under Severe Fuel-Damage Conditions - 01 January 1987

STP28142S: Influence of the Initial Material Condition on the Deformation Behavior of Zircaloy Cladding Tubes in the High-α-Phase Region - 01 January 1987

STP28144S: Study by Thermoelectric Power Measurements of Recovery and Recrystallization of Cold-Rolled Zircaloy-4 Sheets - 01 January 1987

STP28145S: Effect of Metallurgical Variables and Temperature on the Fracture Toughness of Zirconium Alloy Pressure Tubes - 01 January 1987

STP28146S: Cumulative Fatigue and Creep-Fatigue Damage at 350°C on Recrystallized Zircaloy-4 - 01 January 1987

STP28105S: Mechanistic Modeling of Zircaloy Deformation and Fracture in Fuel Element Analysis - 01 January 1987

STP28147S: Cyclic Behavior of Zircaloy-4 at Elevated Temperatures - 01 January 1987

STP28148S: Residual Stresses in Textured Zirconium Alloys - 01 January 1987

STP28149S: Effect of Cold Reduction on Anisotropy of Zircaloy Tubing - 01 January 1987

STP28151S: Cold-Rolled and Annealed Textures of Zircaloy-4 Thin Strips - 01 January 1987

STP28152S: Zirconium-Barrier Cladding Attributes - 01 January 1987

STP28154S: Iodine-Induced Stress Corrosion of Zircaloy Fuel Cladding: Initiation and Growth - 01 January 1987

STP28155S: Recent Studies of Crack Initiation During Stress Corrosion Cracking of Zirconium Alloys - 01 January 1987

STP28156S: Deformation and Fracture Properties of Neutron-Irradiated Recrystallized Zircaloy-2 Cladding under Uniaxial Tension - 01 January 1987

STP28157S: Chemical Inhomogeneity Populations in Various Zircaloy Claddings and Their Association with SCC and Corrosion Resistance - 01 January 1987

STP28158S: Fracture Behavior and Microstructural Characteristics of Irradiated Zircaloy Cladding - 01 January 1987

STP939-EB: Zirconium in The Nuclear Industry: Seventh International Symposium - 01 January 1987

STP28109S: Microstructural Effects on the Irradiation Growth of Zr-2.5Nb - 01 January 1987

STP25625S: Fractography of Pressure Vessel Steel Weldments - 01 January 1987

STP25627S: Fracture Morphology of 13% Chromium Steam Turbine Blading Steel - 01 January 1987

STP19677S: ICP-AES Radioactive Sample Analyses at Pacific Northwest Laboratory - 01 January 1987

STP951-EB: Plasma Spectroscopy for the Analysis of Hazardous Materials: Design and Application of Enclosed Plasma Sources - 01 January 1987

STP19679S: The Los Alamos Facility for Inductively Coupled Plasma Atomic Emission Spectrometric Analysis of Radioactive Solutions - 01 January 1987

STP19680S: Remote Inductively Coupled Plasma Atomic Emission Spectrometry at the Idaho Chemical Processing Plant - 01 January 1987

STP19681S: Development and Layout of an ICP Excitation Unit in a Hot Cell - 01 January 1987

STP19668S: Glove Box Enclosed D-C Plasma Source for the Determination of Metals in Plutonium Solutions - 01 January 1987

STP19669S: A Simplified System for Doing ICP Analysis on Radioactive Samples - 01 January 1987

STP19670S: Use of an Inductively Coupled Plasma Emission Spectrometer System in a Separations Process Plant Laboratory - 01 January 1987

STP19666S: ICP Source Optical Emission Spectroscopy Analysis of Radioactive Materials: A View of the United Kingdom Scene - 01 January 1987

STP19672S: Modification of an Inductively Coupled Plasma Atomic Emission Spectrometer for Analysis of Plutonium Impurities - 01 January 1987

STP19673S: Design for a Contained Inductively Coupled Plasma/D-C Arc Atomic Emission Spectrometer at the Savannah River Plant - 01 January 1987

STP19674S: Five Years of Plasma Emission Spectroscopy (ICP-AES) Analyses of Toxic and Radioactive Materials at the Bruyeres le Chatel Center in France - 01 January 1987

STP19675S: The Ames Laboratory Facility for the Emission Spectroscopic Study of Alpha-Emitting Radionuclei: The Design and Operating History - 01 January 1987

STP19676S: Adaptation of a Beckman Spectraspan VI Spectrometer to a Plutonium Glove Box - 01 January 1987

STP33811S: Irradiation-Induced Swelling in AISI 316 Steel: Effect of Tensile and Compressive Stresses - 01 January 1987

STP955-EB: Radiation-Induced Changes in Microstructure: 13th International Symposium (Part I) - 01 January 1987

STP33812S: Void Swelling and Microstructural Change in Neutron Irradiated Type 316 Stainless Steel - 01 January 1987

STP33813S: Development of Modified Type 316 Stainless Steel for Fast Breeder Reactor Fuel Cladding Tubes - 01 January 1987

STP33814S: Swelling of 316 Stainless Steel and D9 Cladding in FFTF - 01 January 1987

STP33804S: Vacancy Properties During Irradiation with High Energy Particles - 01 January 1987

STP33815S: Neutron-Induced Swelling in Cold-Worked Titanium-Modified AISI 316 Alloys - 01 January 1987

STP33816S: Void-Precipitate Association During Neutron Irradiation of Austenitic Stainless Steel - 01 January 1987

STP33817S: Neutron-Induced Swelling of Fe-Mn and Fe-Cr-Mn Austenitic Alloys - 01 January 1987

STP33818S: The Effect of Swelling in Inconel® 600 on the Performance of FFTF Reflector Assemblies - 01 January 1987

STP33819S: Influence of Grain and Subgrain Boundaries on Void Formation and Growth in Aluminum Irradiated with Fast Neutrons - 01 January 1987

STP33820S: Nucleation, Growth, and Distribution of Cavities in the Vicinity of Grain Boundaries in Aluminum Irradiated with 600-MeV Protons - 01 January 1987

STP33821S: Dislocation Behavior in the Swelling Process of HVEM Irradiated Stainless Steel - 01 January 1987

STP33822S: Void Swelling in Electron-Irradiated Fe-Cr-Ni Model Alloys - 01 January 1987

STP33823S: The Behavior of Solute Segregation and Void Formation in Fe-Cr-Ni and Fe-Cr-Mn Steels During Electron Irradiation - 01 January 1987

STP33824S: Oxygen Effects on Void Stabilization in Stainless Steel - 01 January 1987

STP33805S: A Study of Defect Structures in Fast Neutron Irradiated Nickel and Iron by Measurements of Magnetic Anisotropy - 01 January 1987

STP33826S: The Influence of Both Major and Minor Element Composition on Void Swelling in Austenitic Steels - 01 January 1987

STP33827S: Effect of Nickel Content on the Minimum Critical Void Radius in Ternary Austenitic Alloys - 01 January 1987

STP33828S: The Influence of Helium Trapping by Vacancies on the Behavior of Metals Under Irradiation - 01 January 1987

STP33829S: Transport of Helium to Grain Boundaries During Irradiation - 01 January 1987

STP33830S: A Comparison of the Relative Importance of Helium and Vacancy Accumulation in Void Nucleation - 01 January 1987

STP33831S: A Composite Model of Microstructural Evolution in Austenitic Stainless Steel Under Fast Neutron Irradiation - 01 January 1987

STP33806S: Cascade Defect Production and Irradiation Enhanced Diffusion in Cu3Au - 01 January 1987

STP33832S: Interstitial Dislocation Loop Nucleation and Growth and Swelling Produced By High-Energy Cascades - 01 January 1987

STP33833S: Comparison of Various Sink Strengths for Analyzing Radiation Creep, Growth, and Swelling - 01 January 1987

STP33834S: Gas-Bubble Growth Mechanisms in the Analysis of Metal Fuel Swelling - 01 January 1987

STP33835S: The Effects of Applied Stress on the Irradiation Induced Microstructures of Dilute Nickel Alloys - 01 January 1987

STP33836S: Dislocation Evolution in Fe-10% Cr - 01 January 1987

STP33837S: Stability Studies of Radiation Defects in Aluminum Introduced by 600-MeV Protons - 01 January 1987

STP33807S: The Collapse of Defect Cascades to Dislocation Loops During Self-Ion Irradiations of Iron, Nickel, and Copper at 30, 300, and 600 K - 01 January 1987

STP33838S: In-Situ Electron Microscopy Observation of Dislocation Motion in 600-MeV Proton Irradiated Aluminum - 01 January 1987

STP33839S: Ion Damage in a Fe-10Cr-6Mo-0.5Nb Ferritic Steel - 01 January 1987

STP33840S: Microstructural Changes in Commercial Aluminum Alloys Caused by Irradiation with 800-MeV Protons - 01 January 1987

STP33841S: Effects of Neutron Irradiation on the Microstructure and Microhardness of Niobium-Base Alloys - 01 January 1987

STP33842S: Effects of Heavy-Ion Irradiation on HT-9 Ferritic Steel Examined in Cross Section - 01 January 1987

STP33843S: Microstructural Examination of 12% Cr Martensitic Stainless Steel After Irradiation at Elevated Temperatures in FFTF - 01 January 1987

STP33844S: Evaluation of Ferritic Alloy Fe-2¼Cr-1Mo After Neutron Irradiation: Microstructural Development - 01 January 1987

STP33845S: Nickel Ion Irradiation Effects on the Microstructure of 2 1/4% Cr 1% Mo Steel and a Comparison with Neutron Irradiation Data - 01 January 1987

STP33846S: The Fine Scale Microstructure in Cast and Aged Duplex Stainless Steels Investigated by Small Angle Neutron Scattering - 01 January 1987

STP33803S: Diffusion Coefficients of Nickel and Silicon in Ion Irradiated Fe-20Cr-20Ni - 01 January 1987

STP33808S: The Collapse of Defect Cascades to Dislocation Loops in Cu3Au - 01 January 1987

STP33847S: Radiation-Induced Segregation in Light-Ion Bombarded Ni-8% Si - 01 January 1987

STP33848S: Precipitate Evolution in Type 316 Stainless Steels Irradiated in EBR-II - 01 January 1987

STP33849S: Irradiation-Suppressed Graphite and Cementite Precipitation in Fe-Ni-C and Ni-C Alloys - 01 January 1987

STP33850S: Amorphous Transformation of Laves Phase in Zircaloy and Austenitic Stainless Steel Upon Neutron Irradiation - 01 January 1987

STP33851S: Phase Transformations in Neutron-Irradiated Zircaloys - 01 January 1987

STP33852S: Radiation-Induced Segregation in Cu-Au Alloys - 01 January 1987

STP33809S: Effects of Anisotropic Diffusion on Irradiation Deformation - 01 January 1987

STP33853S: Effect of Irradiation on Carbide Evolution in a Pure Fe-2¼Cr-1Mo Ferritic Alloy - 01 January 1987

STP33854S: Radiation-Induced Segregation and Precipitation in Molybdenum-Rhenium Alloys - 01 January 1987

STP33855S: Solute Segregation and Microstructural Evolution in Ion-Irradiated Vanadium-Base Alloys - 01 January 1987

STP33856S: The Influence of Electron Irradiation on the Structural State of γ-Fe-Mn Alloys - 01 January 1987

STP33857S: Compositional Redistribution in Fe-Ni-Cr Alloys Under Proton Irradiation - 01 January 1987

STP33858S: Phase Stability in Fe-15 Ni-x Cr Alloys Under Ion or Electron Irradiation - 01 January 1987

STP33859S: Neutron-Induced Spinodal-Like Decomposition of Fe-Ni and Fe-Ni-Cr Alloys - 01 January 1987

STP33860S: Spinodal-like Decomposition and Swelling Induced by Ion Irradiation in Simple Fe-Ni and Fe-Ni-Cr Alloys - 01 January 1987

STP33861S: Comparison of Plastic Deformation and Charged Particle Irradiation Influence on Phase Transformations in Stainless Steel - 01 January 1987

STP33862S: Compositional Fluctuations and Stability of Alloys Under Radiation - 01 January 1987

STP33863S: Point Defect Dynamics in Nonhomogenous Alloys Under Irradiation - 01 January 1987

STP33864S: Computer Simulation of Precipitate Recoil Resolution by Energetic Collision Cascades - 01 January 1987

STP33865S: Separation of Alloy Components in the Vicinity of a Collision Cascade - 01 January 1987

STP33866S: Depth Profiling of Hydrogen Isotopes Implanted into TiC Crystals - 01 January 1987

STP33867S: Helium Ion Implantation Induced Damage in Metallic Glasses - 01 January 1987

STP33868S: Study of Heavy and Light Ion Irradiation Induced Effects in Metallic Glass Samples - 01 January 1987

STP33869S: Dose and Energy Dependence of Helium Ion Irradiated Monel-400 - 01 January 1987

STP33810S: Quantitative Study By Field Ion Microscopy of Radiation Damage in Tungsten After Proton and Neutron Irradiation - 01 January 1987

STP25644S: Effects of 14-MeV Neutron Irradiations on Mechanical Properties of Ferritic Steels - 01 January 1987

STP956-EB: Influence of Radiation on Material Properties: 13th International Symposium (Part II) - 01 January 1987

STP25637S: Cessation of Irradiation Creep in AISI 316 Concurrent with High Levels of Swelling - 01 January 1987

STP25645S: Impurity Element Effects on the Toughness of 12 Cr-1 Mo Steel - 01 January 1987

STP25646S: Tensile Properties of Several 800 MeV Proton-Irradiated bcc Metals and Alloys - 01 January 1987

STP25647S: Post-Irradiation Fracture Properties of Precipitation-Strengthened Alloy D21 - 01 January 1987

STP25648S: Mechanical Properties at Low and High Strain Rates of PE 16 Alloys Irradiated to 9.2 dpa - 01 January 1987

STP25649S: J-Integral Toughness of Low Fluence Neutron-Irradiated Stainless Steel DIN 1.4948 - 01 January 1987

STP25650S: Fatigue Crack Growth and Fracture Toughness Properties of Low Fluence Neutron-Irradiated Type 316 and Type 304 Stainless Steels - 01 January 1987

STP25651S: Experimental Assessments of Notch Ductility and Tensile Strength of Stainless Steel Weldments After 120°C Neutron Irradiation - 01 January 1987

STP25652S: Effect of Cold Work on Tensile Behavior of Irradiated Type 316 Stainless Steel - 01 January 1987

STP25653S: Radiation Effects on the Micromechanics of Fatigue Crack Initiation - 01 January 1987

STP25638S: In-Reactor Creep Rupture Behavior of the D19 and 316 Alloys - 01 January 1987

STP25654S: Hydrogen Buildup in Irradiated Type-304 Stainless Steel - 01 January 1987

STP25655S: Mechanical Properties and Fracture Behavior of 20% Cold-Worked 316 Stainless Steel Irradiated to Very High Neutron Exposures - 01 January 1987

STP25656S: The Effect of Neutron Irradiation on the Tensile Properties and Microstructure of Several Vanadium Alloys - 01 January 1987

STP25657S: Tensile and Fracture Properties of EBR-II-Irradiated V-15Cr-5Ti Containing Helium - 01 January 1987

STP25639S: Analysis of the In-Reactor Creep and Rupture Life Behavior of Stabilized Austenitic Stainless Steels and the Nickel-Base Alloy Hastelloy-X - 01 January 1987

STP25658S: The Effects of Temperature and Strain Rate on the Properties of (Fe,Ni)3V LRO Alloys - 01 January 1987

STP25659S: Microstructural Characterization of Submerged Arc Weld Metals - 01 January 1987

STP25660S: Comparison of Irradiation-Induced Transition Temperature Increases from Notch Ductility and Fracture Toughness Tests - 01 January 1987

STP25661S: Comparison of the Effect of Power and Test Reactor Irradiations on the Fracture Properties of Submerged-Arc Welds - 01 January 1987

STP25662S: Investigation of Neutron Irradiated Reactor Pressure Vessel Steel by Positron Annihilation and Electron Microscopy - 01 January 1987

STP25663S: Tensile Properties of Irradiated Pressure Vessel Steels - 01 January 1987

STP25664S: Effect of Interstitial Impurities on Fracture Characteristics of A533-B Class 1 Pressure Vessel Steel - 01 January 1987

STP25665S: Irradiation Embrittlement of Advanced Pressure Vessel Steels - 01 January 1987

STP25666S: A Comparison Between French Surveillance Program Results and Predictions of Irradiation Embrittlement - 01 January 1987

STP25667S: The Effect of Thermal Annealing on the Fracture Properties of a Submerged-Arc Weld Metal - 01 January 1987

STP25668S: Steel Impurity Element Effects on Postirradiation Properties Recovery by Annealing - 01 January 1987

STP25669S: A Study of Radiation Induced Voids and Precipitates and Their Annealing Behavior by Small-Angle Neutron Scattering - 01 January 1987

STP25670S: Irradiation Embrittlement Evaluation Without Lateral Expansion Measurements - 01 January 1987

STP25671S: Trend Curve Data Development and Testing - 01 January 1987

STP25672S: Damage Rate and Spectrum Effects in Ferritic Steel ΔNDTT Data - 01 January 1987

STP25640S: In-Reactor Deformation of Zr-2.5 wt% Nb Pressure Tubes - 01 January 1987

STP25673S: Current Limitations of Trend Curve Analysis for the Prediction of Reactor PV Embrittlement - 01 January 1987

STP25674S: A Statistical Analysis of Fracture Toughness of Irradiated Low-Alloy Steel Plate and Welds - 01 January 1987

STP25675S: Fission Fragment Damage in Ceramic Nuclear Fuels - 01 January 1987

STP25636S: Radiation-Induced Creep of Aluminum and Copper - 01 January 1987

STP25676S: Fission Fragment Induced Hardening in Uranium Mononitride - 01 January 1987

STP25677S: The Assessment of Seal Performance and Lifetime Prediction in a Nuclear Environment - 01 January 1987

STP25678S: The Effects of Radiation on Organic Matrix Waste Forms - 01 January 1987

STP25679S: Hydrogen Control in the Handling, Shipping, and Storage of Wet Radioactive Waste - 01 January 1987

STP25680S: Photobleaching Effects on Radiation-Induced Loss for Silica Glass Image Fiber - 01 January 1987

STP25681S: Irradiation Devices for Reactor Materials: Results Obtained from Irradiated Lithium Aluminate at the OSIRIS Reactor - 01 January 1987

STP25682S: Irradiation Effects in KAPTON Polyimide Film from 14-MeV Neutrons and Cobalt-60 Gamma Rays - 01 January 1987

STP25683S: Changes in Surface Morphology and Microcrack Initiation in Polymers Under Simultaneous Exposure to Stress and Fast Atom Bombardment - 01 January 1987

STP25684S: Effect of Gamma Radiation on the Permeability of Opthalmic Preservatives Through Fluorine Surface-Treated Low-Density Polyethylene Bottles - 01 January 1987

STP25641S: Light-Ion Irradiation Creep and Hardening of Model Ferritic Alloys - 01 January 1987

STP25685S: The Low-Temperature Neutron Irradiation Facility at ORNL - 01 January 1987

STP25686S: Irradiation Facilities at the Idaho National Engineering Laboratory - 01 January 1987

STP25687S: Operating Experience at the Los Alamos Spallation Radiation Effects Facility at LAMPF - 01 January 1987

STP25688S: Additional Measurements of the Radiation Environment at the Los Alamos Spallation Radiation Effects Facility at LAMPF - 01 January 1987

STP25689S: Recent Research in Neutron Dosimetry and Damage Analysis for Materials Irradiations - 01 January 1987

STP25690S: Improvement of Accuracy Assessment in Radiation Damage Predictions - 01 January 1987

STP25691S: Comparison of Calculated Integral Values Using Measured and Calculated Neutron Spectra for Fusion Neutronics Analyses - 01 January 1987

STP25692S: Measurements of 10B(n,He) Reaction Rates in a Mockup Control Rod in ZPPR - 01 January 1987

STP25693S: Spectrum Integrated (n,He) Cross Section Comparison and Least Squares Analysis for 6Li and 10B in Benchmark Fields - 01 January 1987

STP25642S: The Ductile-to-Brittle Transition Behavior of Martensitic Steels Neutron Irradiated to 26 dpa - 01 January 1987

STP25643S: Effects of Microstructure and Thermal Aging on Neutron Irradiation Embrittlement of 2¼Cr-1Mo Steel for a Nuclear Pressure Vessel - 01 January 1987

STP32998S: Shear Punch and Microhardness Tests for Strength and Ductility Measurements - 01 January 1986

STP888-EB: The Use of Small-Scale Specimens for Testing Irradiated Material - 01 January 1986

STP32999S: Low-Load Microhardness Changes in 14-MeV Neutron Irradiated Copper Alloys - 01 January 1986

STP33000S: Effects of Specimen Thickness and Grain Size on the Mechanical Properties of Types 304 and 316 Austenitic Stainless Steel - 01 January 1986

STP33001S: Failure Strain for Irradiated Zircaloy Based on Subsized Specimen Testing and Analysis - 01 January 1986

STP32993S: Miniaturized Disk Bend Test Technique Development and Application - 01 January 1986

STP33003S: Wire Tensile Testing for Radiation-Hardening Experiments - 01 January 1986

STP33004S: Design and Use of Nonstandard Tensile Specimens for Irradiated Materials Testing - 01 January 1986

STP33006S: Comparison of Mechanical Properties in Thin Specimens of Stainless Steel with Bulk Material Behavior - 01 January 1986

STP33007S: A Miniaturized Mechanical Testing System for Small-Scale Specimen Testing - 01 January 1986

STP33008S: Post-Irradiation Creep Properties of Cold-Worked 316 Stainless Steel As Measured with Small Creep Specimens - 01 January 1986

STP33009S: Miniature Center-Cracked-Tension Specimen for Fatigue Crack Growth Testing - 01 January 1986

STP33010S: Use of Subsize Fatigue Specimens for Reactor Irradiation Testing - 01 January 1986

STP33011S: Use of Subsized Specimens for Evaluating the Fracture Toughness of Irradiated Materials - 01 January 1986

STP33012S: Subsized Bend and Charpy V-Notch Specimens for Irradiated Testing - 01 January 1986

STP33014S: Effect of Specimen Size and Material Condition on the Charpy Impact Properties of 9Cr-1Mo-V-Nb Steel - 01 January 1986

STP33015S: Specimen-Size Considerations in Crack-Arrest Testing of Irradiated RPV Steels - 01 January 1986

STP33016S: Experience in Subsized Specimen Testing - 01 January 1986

STP32994S: The MIT Miniaturized Disk Bend Test - 01 January 1986

STP32992S: Use of the Disk Bend Test to Assess Irradiation Performance of Structural Alloys - 01 January 1986

STP32995S: Disk-Bend Ductility Tests for Irradiated Materials - 01 January 1986

STP32997S: Development of Small Punch Tests for Ductile-Brittle Transition Temperature Measurement of Temper Embrittled Ni-Cr Steels - 01 January 1986

STP33057S: A Conceptual Framework to Guide Aquatic Monitoring Program Design for Thermal Electric Power Plants - 01 January 1986

STP17355S: New 2Cr-Mo-Ni-W-V Steel for High-Pressure Rotors - 01 January 1986

STP17356S: Mechanical Properties of Advanced Technology 1Cr-Mo-V Steam Turbine Rotor Forgings - 01 January 1986

STP17357S: Soft-Martensitic Stainless Cr-Ni-Mo Steel for Turbine Rotors in Geothermic Power Stations - 01 January 1986

STP17358S: Metallurgical Analysis of Flaws in Carbon-Molybdenum and Nickel-Molybdenum-Vanadium Turbine Rotor Forgings - 01 January 1986

STP17359S: The Fracture Toughness of Actual and Simulated Large Rotor Forgings Made from 3.5Ni Steel - 01 January 1986

STP17360S: Integrity of Full-Integral, Low-Pressure Nuclear Turbine Forgings - 01 January 1986

STP17361S: In-Service Inspection Test and Evaluation Techniques for Large Generator Rotors - 01 January 1986

STP17362S: The Development of New Materials for Nonmagnetizable Retaining Rings and Other Applications in the Power Generating Industry - 01 January 1986

STP17363S: 18—18 Corrosion-Resistant Retaining Rings for Nuclear Power Plant Generators - 01 January 1986

STP17364S: Seamless Shell Course Forgings For Heavy-Wall Reactor Vessels: A Forgemaster's Critical Review - 01 January 1986

STP17350S: Influence of Advanced Steelmaking Technology on Specification Trends for Rotor Forgings - 01 January 1986

STP17368S: Application of New Types of Ingots to the Manufacturing of Heavy Pressure Vessel Forgings - 01 January 1986

STP17369S: Integral Forged Pump Casing for the Primary Coolant Circuit of a Nuclear Reactor: Development in Design, Forging Technology, and Material - 01 January 1986

STP17370S: Manufacturing of Large and Integral-Type Steel Forgings for Nuclear Steam Supply System Components - 01 January 1986

STP17371S: Advanced Technology of Heavy-Section Tube Sheets for Nuclear Power Generation - 01 January 1986

STP17373S: Production of a 304 Stainless Steel Nuclear Reactor Forging from a Very Large Electroslag Refined Ingot - 01 January 1986

STP17377S: Cryogenic Mechanical Properties of A286 Alloy and 304LN Stainless Steel Used in Fabrication of Support Struts for Superconducting Magnets - 01 January 1986

STP17352S: Development of Integral High-Pressure—Low-Pressure Combination Rotor Forgings - 01 January 1986

STP17353S: Manufacture of Differentially Heat-Treated Turbine Rotor Forgings - 01 January 1986

STP17354S: Manufacturing of Welded Polyblock Turbine Rotors for Pressurized Water Reactor Nuclear Plants; Optimization of the Steel Grade; Effect of Impurities - 01 January 1986

STP17349S: The Development of Improved Forgings for Modern Steam Turbines - 01 January 1986

STP19640S: Measurements of Air Infiltration and Airtightness in Passive Solar Homes - 01 January 1986

STP17408S: Fracture Toughness Testing of Zircaloy-2 Pressure Tube Material with Radial Hydrides Using Direct-Current Potential Drop - 01 January 1986

STP17387S: Variable Flaw Shape Analysis for a Reactor Vessel under Pressurized Thermal Shock Loading - 01 January 1986

STP17454S: On-Line Monitoring of the True Corrosion Rate in Problems Related to Power Plants - 01 January 1986

STP17455S: Waterside Corrosion Control During Operation of Drum-Type Utility Boilers - 01 January 1986

STP23031S: Boiling Water Reactor (BWR) Pressure Vessel Surveillance Program - 01 January 1986

STP909-EB: Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Second Volume) - 01 January 1986

STP23032S: Static Fracture Criteria Evaluation Using Small Specimens - 01 January 1986

STP23033S: Investigations and Measures to Guarantee the Safety of a Pressurized Water Reactor's Pressure Vessel Against Brittle Fracture - 01 January 1986

STP23026S: Overview of Studies in the United Kingdom on Neutron Irradiation Embrittlement of Pressure Vessel Steels - 01 January 1986

STP23034S: Basis for Revision 2 of the U. S. Nuclear Regulatory Commission's Regulatory Guide 1.99 - 01 January 1986

STP23035S: Reactor Pressure Vessel Structural Implications of Embrittlement to the Pressurized-Thermal-Shock Scenario - 01 January 1986

STP23036S: Safety Standard KTA 3203: Monitoring Radiation Embrittlement of Reactor Pressure Vessels of Light-Water Reactors - 01 January 1986

STP23037S: Microanalytical Studies of Pressure Vessel Weld Materials - 01 January 1986

STP23038S: Irradiation Embrittlement of Reactor Pressure Vessel Steels: Mechanisms, Models, and Data Correlations - 01 January 1986

STP23039S: Annealing and Reirradiation Response of Irradiated Pressure Vessel Steels - 01 January 1986

STP23040S: Effect of Various Metallurgical Microstructures on the Response of the Nickel-Molybdenum-Chromium BH 70 Steel to Neutron Irradiation at 285°C - 01 January 1986

STP23027S: Irradiation Behavior of Reactor Pressure Vessel Steels from the Research Program on the Integrity of Components - 01 January 1986

STP23028S: Surveillance Programs and Irradiation Embrittlement Research of the Loviisa Nuclear Power Plant - 01 January 1986

STP23025S: Irradiation Effects in Reactor Pressure Vessel Steels: A Nuclear Regulatory Commission Perspective - 01 January 1986

STP23029S: Effect of Irradiation on the Elasto-Plastic Toughness of Pressure Vessel Steels - 01 January 1986

STP23030S: Prediction of Reference Transition Temperature Increase Due to Neutron Irradiation Exposure - 01 January 1986

STP18371S: Turbine Lubricant Oxidation: Testing, Experience, and Prediction - 01 January 1986

STP19329S: Choosing a Steel for Hydroelectric Penstocks - 01 January 1986

STP19325S: Cracking at Nozzle Corners in the Nuclear Pressure Vessel Industry - 01 January 1986

STP19324S: Use of Material Characterization to Complement Fracture Mechanics in the Analysis of Two Pressure Vessels for Further Service in a Hydrogenating High-Temperature Process - 01 January 1986

STP19326S: A Pressure Vessel Hatch Cover Failure: A Design Analysis - 01 January 1986

STP19328S: Analysis of the Unstable Fracture of a Reactor Pressure Tube Using Fracture Toughness Mapping - 01 January 1986

STP18394S: Evaluation of Valid Nil-Ductility Transition Temperatures for Nuclear Vessel Steels - 01 January 1986

STP42094S: Filter Tests to Support Gas Turbine Applications - 01 January 1986

STP42097S: The Need for Standard Test Methods for Fiberglass Fabrics Used on Utility Coal-Fired Boilers - 01 January 1986

STP36231S: The Role of Fretting in the Initiation and Early Growth of Fatigue Cracks in Turbo-Generator Materials - 01 January 1985

STP36237S: Biaxial/Torsional Fatigue of Turbine-Generator Rotor Steels - 01 January 1985

STP32803S: Short Fiber Reinforced Magnetic Powder Cores - 01 January 1985

STP34260S: Axial Fracture Toughness Testing of Zr-2.5Nb Pressure Tube Material - 01 January 1985

STP34276S: Elastic-Plastic Failure Analysis of Pressure Vessel Tests - 01 January 1985

STP34277S: Fracture Mechanics Analysis of a Pressure Vessel with a Semi-Elliptical Surface Crack Using Elastic-Plastic Finite Element Calculations - 01 January 1985

STP37356S: Effect of Irradiation Temperature on the Precipitation in Cold-Worked Titanium-Stabilized Type 316 Stainless Steel - 01 January 1985

STP870-EB: Effects of Radiation on Materials: Twelfth International Symposium - 01 January 1985

STP37357S: Microstructure of Irradiated Inconel 706 Fuel Pin Cladding - 01 January 1985

STP37358S: Microsegregation Observed in Fe-35.5Ni-7.5Cr Irradiated in EBR-II - 01 January 1985

STP37359S: Transmission Electron Microscope Studies and Microhardness Testing of Irradiated Ferritic Steels - 01 January 1985

STP37360S: Phase Stability in Irradiated Alloys by Constrained Equilibrium Thermodynamics - 01 January 1985

STP37361S: Swelling of Austenitic Iron-Nickel-Chromium Ternary Alloys During Fast Neutron Irradiation - 01 January 1985

STP37350S: Evaluation of Ferritic Alloy Fe-2¼Cr-1Mo After Neutron Irradiation: Irradiation Creep and Swelling - 01 January 1985

STP37362S: Swelling of 20% Cold-Worked Type 316 Stainless Steel Fuel Pin Cladding and Ducts - 01 January 1985

STP37363S: Swelling of AISI Type 304L Stainless Steel in Response to Simultaneous Variations in Stress and Displacement Rate - 01 January 1985

STP37364S: Some Observations on the Effect of Stress on Irradiation-Induced Swelling in AISI Type 316 Stainless Steel - 01 January 1985

STP37365S: Swelling of Microstructure of Neutron-Irradiated Titanium-Modified Type 316 Stainless Steel - 01 January 1985

STP37366S: Role of Dislocations, Dislocation Walls, and Grain Boundaries in Void Formation During Early Stages of Fast Neutron Irradiation - 01 January 1985

STP37367S: Influence of Applied Stress on Swelling Behavior in Type 304 Stainless Steel - 01 January 1985

STP37368S: Evolution of Cavity Microstructure in Ion-Irradiated Type 316 Stainless Steel and Fe-20Ni-15Cr Alloy - 01 January 1985

STP37369S: Experimental Investigation of the Effect of Injected Interstitials on Void Formation - 01 January 1985

STP37370S: Influence of Helium on Swelling of Steels - 01 January 1985

STP37371S: Comparison of Depth-Dependent Microstructures of Ion-Irradiated Type 316 Stainless Steels - 01 January 1985

STP37372S: Experimental Determination of the Critical Cavity Radius in Fe-10Cr for Ion Irradiation - 01 January 1985

STP37373S: Comparison of Thermal and Irradiated Behavior of High-Strength, High-Conductivity Copper Alloys - 01 January 1985

STP37374S: Ion Bombardment Damage in a Modified Fe-9Cr-1Mo Steel - 01 January 1985

STP37351S: Influence of a Temperature Change on In-Reactor Creep - 01 January 1985

STP37375S: Helium and Displacement Damage Produced by 600 MeV Proton Beams in High Purity Aluminum - 01 January 1985

STP37376S: Direct Observation of Cascade Defect Formation at Low Temperatures in Ion-Irradiated Metals - 01 January 1985

STP37377S: Solute Segregation and Void Formation on Grain Boundaries in Electron-Irradiated Type 316 Stainless Steel - 01 January 1985

STP37378S: Nonequilibrium Segregation and Phase Instability in Alloy Films During Elevated-Temperature Irradiation in a High-Voltage Electron Microscope - 01 January 1985

STP37379S: Modeling of Void Swelling in Irradiated Steels - 01 January 1985

STP37380S: Influence of Composition on Steady-State Void Nucleation in Irradiated Alloys - 01 January 1985

STP37381S: Effect of Microstructure on the Minimum Critical Radius and Critical Number of Gas Atoms for Swelling - 01 January 1985

STP37382S: Dual-Ion Irradiation: Impact of the Conflicting Roles of Helium on Void Nucleation - 01 January 1985

STP37383S: Nucleation of Voids—The Impurity Effect - 01 January 1985

STP37384S: A Mechanism of Void Lattice Formation Based on Two-Dimensional Self-Interstitial Diffusion - 01 January 1985

STP37352S: Non-Isothermal In-Reactor Creep of Nickel Alloys Inconel 706 and PE-16 - 01 January 1985

STP37353S: In-Pile Creep Strain and Failure of Cold-Worked Type 316 Titanium Pressurized Tubes - 01 January 1985

STP37354S: Critical Assessment of Low-Fluence Irradiation Creep Mechanisms - 01 January 1985

STP37349S: In-Reactor Creep of Selected Ferritic Alloys - 01 January 1985

STP37355S: Irradiation-Creep-Induced Anisotropy in a/2 <110> Dislocation Populations - 01 January 1985

STP34432S: A Fracture Mechanics Model for Iodine Stress Corrosion Crack Propagation in Zircaloy Tubing - 01 January 1984

STP34447S: Automated Corrosion Fatigue Crack Growth Testing in Pressurized Water Environments - 01 January 1984

STP34465S: Analytical Approaches and Experimental Verification to Describe the Influence of Cold Work and Heat Treatment on the Mechanical Properties of Zircaloy Cladding Tubes - 01 January 1984

STP34467S: On-Line Ultrasonic Inside-Diameter Control System for Zircaloy Tube Etching - 01 January 1984

STP34468S: Variation in the Strain Anisotropy of Zircaloy with Temperature and Strain - 01 January 1984

STP34469S: A Study on the Nonelastic Behavior of Zircaloy Fuel Cladding - 01 January 1984

STP34471S: On the Short-Time Recrystallization of Zircaloy-4 Above 600°C - 01 January 1984

STP34472S: Orientation of Hydrides in Zirconium Alloy Tubes - 01 January 1984

STP34473S: Correlation Between Fabrication Parameters, Microstructure, and Texture in Zircaloy Tubing - 01 January 1984

STP34474S: On the Texture Measurements for Zircaloy Cladding Tube - 01 January 1984

STP34475S: Texture Effect of Zircaloy on Ultrasonic Velocity - 01 January 1984

STP34476S: In-Reactor Creep of Zr-2.5Nb - 01 January 1984

STP34477S: Influence of Metallurgical Condition on the In-Reactor Dimensional Changes of Zircaloy Fuel Rods - 01 January 1984

STP34478S: Deformation Characteristics of Cold-Worked and Recrystallized Zircaloy-4 Cladding - 01 January 1984

STP34479S: Irradiation Creep and Growth During Proton and Neutron Bombardment of Zircaloy-2 Plate - 01 January 1984

STP34481S: Irradiation Growth of Annealed Zircaloy-2 - 01 January 1984

STP34482S: Irradiation-Induced Dimensional Changes in Polycrystalline Iodide Zirconium and Zircaloy-2 - 01 January 1984

STP34484S: High-Fluence Irradiation Growth of Zirconium Alloys at 644 to 725 K - 01 January 1984

STP34486S: Irradiation Growth of Zircaloy (LWBR Development Program) - 01 January 1984

STP34487S: Characterization of ZrO2 Films Formed In-Reactor and Ex-Reactor to Study the Factors Contributing to the In-Reactor Waterside Corrosion of Zircaloy - 01 January 1984

STP34489S: Improved Characterization of Aqueous Corrosion Kinetics of Zircaloy-4 - 01 January 1984

STP34490S: Effect of Lithium Hydroxide on the Corrosion Behavior of Zircaloy-4 - 01 January 1984

STP34495S: Out-of-Pile Nickel Alloy-Induced Accelerated Hydriding of Zircaloy Fasteners - 01 January 1984

STP34461S: Electron-Beam Remelting of Zircaloys - 01 January 1984

STP34497S: Modeling of Zircaloy Stress-Corrosion Cracking: Texture Effects and Dry Storage Spent Fuel Behavior - 01 January 1984

STP34498S: Influence of Crystallographic Texture and Test Temperature on Initiation and Propagation of Iodine Stress-Corrosion Cracks in Zircaloy - 01 January 1984

STP34502S: Effect of Bundle Size on Cladding Deformation in LOCA Simulation Tests - 01 January 1984

STP34504S: Deformation and Failure of Zircaloy Fuel Sheaths Under LOCA Conditions - 01 January 1984

STP34505S: Estimation of Conservatism of Present Embrittlement Criteria for Zircaloy Fuel Cladding Under LOCA - 01 January 1984

STP34506S: Out-of-Pile Experiments on the High-Temperature Behavior of Zircaloy-4 Clad Fuel Rods - 01 January 1984

STP34507S: Comparison of High-Temperature Steam Oxidation Kinetics Under LWR Accident Conditions: Zircaloy-4 Versus Austenitic Stainless Steel No. 1.4970 - 01 January 1984

STP34508S: Fuel Rod Deformation in LOCA and Severe Core Damage Accidents - 01 January 1984

STP34509S: High-Temperature Oxidation of Zircaloy in Hydrogen-Steam Mixtures - 01 January 1984

STP34510S: Physical and Chemical Phenomena Associated with the Dissolution of Solid UO2 by Molten Zircaloy-4 - 01 January 1984

STP34464S: Pressure Tube Development for CANDU Reactors - 01 January 1984

STP37119S: Fractographic Analysis of the Primary Oil Pump Shaft Fracture from a Steam Turbine - 01 January 1984

STP37120S: Fractographic Analysis of a Steam Turbine Disk Failure - 01 January 1984

STP37121S: Failure Analysis of a Hydraulic Turbine Shaft - 01 January 1984

STP32562S: Temperature Dependence of Fracture Toughness of Large Steam Turbine Forgings Produced by Advanced Steel Melting Processes - 01 January 1984

STP32566S: Microstructural Aspects of the Fracture Toughness Cleavage-Fibrous Transition for Reactor-Grade Steel - 01 January 1984

STP36818S: Lateral-Load Tests on Drilled Pier Foundations for Solar Plant Heliostats - 01 January 1984

STP44836S: Chapter 3 Generic Organic and Inorganic Linings - 01 January 1984

STP837-EB: Manual of Protective Linings for Flue Gas Desulfurization Systems - 01 January 1984

STP44837S: Chapter 4 Design and Fabrication of System Components - 01 January 1984

STP44838S: Chapter 5 Suggested Tests for Evaluating Lining Materials - 01 January 1984

STP44834S: Chapter 1 General Considerations - 01 January 1984

STP44839S: Chapter 6 Lining Material Data - 01 January 1984

STP44840S: Chapter 7 Installation - 01 January 1984

STP44835S: Chapter 2 Operating and Service Conditions - 01 January 1984

STP32684S: Equalization of Axial Neutron Flux Density for the Transmutation Doping of Silicon in a Heavy Water Reactor - 01 January 1984

STP37837S: Morphology and Molecular Structure of Polymers and Their Dielectric Behavior - 01 January 1983

STP783-EB: Engineering Dielectrics Volume IIA Electrical Properties of Solid Insulating Materials: Molecular Structure and Electrical Behavior - 01 January 1983

STP37835S: Introduction - 01 January 1983

STP37838S: Conduction Processes in Polymers - 01 January 1983

STP37839S: Treeing in Solid Organic Dielectric Materials - 01 January 1983

STP37836S: Dielectric Loss in Solids - 01 January 1983

STP37840S: Breakdown Strength of Solids - 01 January 1983

STP37841S: Composition and Structure of Dielectric Solids - 01 January 1983

STP37842S: Radiation Effects on the Electrical Properties of Solid Insulation - 01 January 1983

STP37843S: Composite Insulating Materials and Systems - 01 January 1983

STP29422S: Chapter 4—The General Electric Company Surveillance Programs for Boiling Water Reactor Pressure Vessels - 01 January 1983

STP784-EB: Status of USA Nuclear Reactor Pressure Vessel Surveillance for Radiation Effects - 01 January 1983

STP29423S: Chapter 5—The Westinghouse Electric Corporation Reactor Vessel Radiation Surveillance Program - 01 January 1983

STP29420S: Chapter 2—The Babcock & Wilcox Company Reactor Vessel Surveillance Programs - 01 January 1983

STP29424S: Chapter 6—The General Atomic Company High-Temperature Gas-Cooled Reactor Surveillance Program - 01 January 1983

STP29419S: Chapter 1—The Bases for Surveillance Programs - 01 January 1983

STP29425S: Chapter 7—The Utility Industry and Reactor Surveillance - 01 January 1983

STP29426S: Chapter 8–Review and Analysis of Reactor Vessel Surveillance Programs - 01 January 1983

STP29421S: Chapter 3—Radiation Surveillance Program for Combustion Engineering, Inc. Reactor Vessel Materials - 01 January 1983

STP29444S: Life-Cycle Cost Economic Optimization of Insulation, Infiltration, and Solar Aperture in Energy-Efficient Houses - 01 January 1983

STP29492S: Finite-Difference Thermal Analysis of an Insulation System on a Precipitator Building in a Power Plant - 01 January 1983

STP37079S: Influence of Nonuniform Thermal Stresses on Fatigue Crack Growth of Part-Through Cracks in Reactor Piping - 01 January 1983

STP31770S: Application of Bainite and Ferrite-Martensite Structure for High-Strength Heavy-Gage Linepipe - 01 January 1983

STP31771S: Effect of Microstructure on Sulfide-Stress-Cracking Resistance of High-Strength Casing Steels - 01 January 1983

STP31773S: Improvement of Submerged-Arc Weld Heat-Affected Zone Toughness by Titanium Additions to Linepipe Steels - 01 January 1983

STP31775S: Variation in the Microstructure of Electrodeposited Black Chrome Solar Coatings - 01 January 1983

STP31778S: Development of Low-Cost Polymers for Solar Energy Applications - 01 January 1983

STP31765S: A Caustic Stress-Corrosion Cracking Evaluation of Thermally Treated Inconel Alloy 600 Steam Generator Tubing - 01 January 1983

STP31766S: Research Toward New Alloys for Generator Retaining Rings - 01 January 1983

STP31762S: Tailoring Ti-6Al-4V Alloy for Energy Applications - 01 January 1983

STP44817S: Fractography and Mechanisms of Environmentally Enhanced Fatigue Crack Propagation of a Reactor Pressure Vessel Steel - 01 January 1983

STP33516S: Changes in the Fish Community of the Wabash River Following Power Plant Start-Up: Projected and Observed - 01 January 1983

STP36764S: Development of a Plastic Fracture Methodology for Nuclear Systems - 01 January 1983

STP36766S: Verification of Tearing Modulus Methodology for Application to Reactor Pressure Vessels with Low Upper-Shelf Fracture Toughness - 01 January 1983

STP36774S: Engineering Methods for the Assessment of Ductile Fracture Margin in Nuclear Power Plant Piping - 01 January 1983

STP36789S: A Method of Application of Elastic-Plastic Fracture Mechanics to Nuclear Vessel Analysis - 01 January 1983

STP36796S: Micromechanisms of Ductile Stable Crack Growth in Nuclear Pressure Vessel Steels - 01 January 1983

STP36798S: J-R Curve Characterization of Irradiated Low-Shelf Nuclear Vessel Steels - 01 January 1983

STP29504S: Future Distillate Fuel Trends in Canada and Some Preliminary Gas Turbine Test Results on Tar Sand Products - 01 January 1983

STP809-EB: Stationary Gas Turbine Alternative Fuels - 01 January 1983

STP29505S: Properties of Synthetic Fuels Evaluated for Combustion Turbines - 01 January 1983

STP29506S: Effect of Sodium and Potassium on the Hot Corrosion of Gas Turbines - 01 January 1983

STP29507S: Corrosion of Fuel Handling System Materials by Coal-Derived Liquid Fuels - 01 January 1983

STP29508S: Synthetic Fuels for Stationary Gas Turbines: A California Perspective - 01 January 1983

STP29509S: Distillate Fuels from Nonpetroleum Sources - 01 January 1983

STP29499S: Literature Survey of the Properties of Synthetic Fuels Derived from Coal - 01 January 1983

STP29510S: Coal Gasification for Stationary Gas Turbine Applications - 01 January 1983

STP29511S: A Projection of Coal Gas Properties Considered from the Viewpoint of a Coal Gas Combined-Cycle Plant - 01 January 1983

STP29512S: Properties of Low-Btu Coal Gas and Its Combustion Products - 01 January 1983

STP29513S: Sulfur Measurement in Liquid and Gaseous Alternative Fuels - 01 January 1983

STP29514S: Characterization of Ash Residues from a Refuse-Derived Fuel/Oil Combustion Study - 01 January 1983

STP29515S: Heating Values of Natural Gas and Its Components: Conversion of Values to Measurement Bases and Calculation of Mixtures - 01 January 1983

STP29516S: Measurement Techniques for Fuel Stability Characterization - 01 January 1983

STP29500S: Gas Turbine Fuel Processing Costs and On-Site Cleanup Options - 01 January 1983

STP29498S: Survey of Gas Turbine Synthetic Liquid Fuels - 01 January 1983

STP29501S: Fuel Property Effects on the Performance of a Small Industrial Gas Turbine Engine - 01 January 1983

STP29502S: Performance of SRC-II Fuels in Gas Turbine Combustors - 01 January 1983

STP29503S: Effect of Fuel Properties on Ignition and Combustion Limits in Gas Turbine Combustors - 01 January 1983

STP35205S: Determination of Autogenous Ignition Temperatures of a Steam Turbine Lubricating Oil in Nitrogen and Oxygen Mixtures - 01 January 1983

STP28561S: Inspections, Tests, and Accreditation Activities Associated with Qualification of Safety-Related Equipment for Nuclear Generating Stations - 01 January 1983

STP34414S: Generalizing Creep Equations - 01 January 1983

STP815-EB: Creep of Zirconium Alloys in Nuclear Reactors - 01 January 1983

STP34415S: Verification - 01 January 1983

STP34416S: Four Applications of Creep - 01 January 1983

STP34417S: Designing for Uncertainties - 01 January 1983

STP34410S: Thermal Creep - 01 January 1983

STP34418S: Appendix I—Zirconium Alloy Properties - 01 January 1983

STP34411S: Irradiation Damage - 01 January 1983

STP34412S: Irradiation Creep - 01 January 1983

STP34413S: Descriptions of Creep - 01 January 1983

STP819-EB: Radiation Embrittlement and Surveillance of Nuclear Reactor Pressure Vessels: An International Study - 01 January 1983

STP31850S: Status of Knowledge of Radiation Embrittlement in U.S. Reactor Pressure Vessel Steels - 01 January 1983

STP31851S: Irradiation Experiments in the Testing Nuclear Power Plant VAK - 01 January 1983

STP31852S: Role of the Active Defect Complex in the Neutron Embrittlement and Thermal Recovery of High-Copper Reactor Pressure Vessel Steels - 01 January 1983

STP31853S: Survey of Utility Experience with Reactor Vessel Surveillance - 01 January 1983

STP31854S: Thermal Aging Capsule Results from Oconee Nuclear Station—Unit 1 - 01 January 1983

STP31855S: Assessing Steady-State Neutron Exposure Effects Through Analyses of Reactor Vessel Surveillance Data - 01 January 1983

STP31856S: Selection of Specimen Types for Irradiation Surveillance Programs - 01 January 1983

STP31845S: West German Research Programs on Irradiation Effects on Reactor Pressure Vessels - 01 January 1983

STP31857S: A Fracture Energy Criterion for Irradiation Research and Surveillance - 01 January 1983

STP31858S: Problems in the Evaluation of Reactor Vessel Surveillance Capsules - 01 January 1983

STP31859S: A Service Laboratory's View of the Status and Direction of Reactor Vessel Surveillance - 01 January 1983

STP31846S: Irradiation Embrittlement of Pressure Vessel Steels: A Review of Activities in France - 01 January 1983

STP31847S: Determination of Neutron Damage Parameters for Irradiation Embrittlement - 01 January 1983

STP31844S: NRC Safety Research Priorities for Reactor Vessel Embrittlement, Annealing, and Surveillance Dosimetry - 01 January 1983

STP31848S: Effect of Irradiation on Elastic-Plastic Toughness of Pressure Vessel Steels - 01 January 1983

STP31849S: Specific Problems of Reactor Pressure Vessels Related to Irradiation Effects - 01 January 1983

STP37050S: Long-Term Test Results of Promising New Zirconium Alloys - 01 January 1982

STP37051S: Clad Failure Modeling - 01 January 1982

STP37052S: Chemical Aspects of Iodine-Induced Stress Corrosion Cracking of Zircaloys - 01 January 1982

STP37053S: Effect of Zirconium Oxide on the Stress-Corrosion Susceptibility of Irradiated Zircaloy Cladding - 01 January 1982

STP37054S: Effects of Temperature and Pressure on the In-Reactor Creepdown of Zircaloy Fuel Cladding - 01 January 1982

STP37055S: High-Strength, Creep-Resistant Excel Pressure Tubes - 01 January 1982

STP37056S: High-Temperature Irradiation Growth in Zircaloy - 01 January 1982

STP37057S: Zircaloy-4 Cladding Deformation During Power Reactor Irradiation - 01 January 1982

STP37044S: Texture Control of Zircaloy Tubing During Tube Reduction - 01 January 1982

STP37058S: Burst Criterion of Zircaloy Fuel Claddings in a Loss-of-Coolant Accident - 01 January 1982

STP37059S: An Experimental Study of the Deformation of Zircaloy PWR Fuel Rod Cladding Under Mainly Convective Cooling - 01 January 1982

STP37060S: Effect of Hydrogen on the Oxygen Embrittlement of Beta-Quenched Zircaloy-4 Fuel Cladding - 01 January 1982

STP37061S: Lifetime and Failure Strain Prediction for Material Subjected to Non-stationary Tensile Loading Conditions; Applications to Zircaloy-4 - 01 January 1982

STP37062S: Flow Stress of Oxygen-Enriched Zircaloy-2 Between 1023 and 1873 K - 01 January 1982

STP37063S: A Comparison of the High-Temperature Oxidation Behavior of Zircaloy-4 and Pure Zirconium - 01 January 1982

STP37045S: Texture Measurement Techniques for Zircaloy Cladding: A Round-Robin Study - 01 January 1982

STP37064S: Mechanism of Accelerated Corrosion in Zircaloy-4 Laser and Electron-Beam Welds - 01 January 1982

STP37065S: Waterside Corrosion of Zircaloy-Clad Fuel Rods in a PWR Environment - 01 January 1982

STP37066S: Long-Term In-Reactor Corrosion and Hydriding of Zircaloy-2 Tubing - 01 January 1982

STP37067S: Summary - 01 January 1982

STP37043S: A Review of Texture and Texture Formation in Zircaloy Tubing - 01 January 1982

STP37047S: Application of Hydrostatic Extrusion to Fabrication of Zircaloy Tubing - 01 January 1982

STP37048S: Beta-Quenching of Zircaloy Cladding Tubes in Intermediate or Final Size—Methods to Improve Corrosion and Mechanical Properties - 01 January 1982

STP37049S: New Intermetallic Compounds in Zircaloy-4 - 01 January 1982

STP28412S: Fatigue Crack Propagation in the Heat-Affected Zone of 2¼Cr-1Mo Steel and ERNiCr-3 Weldments - 01 January 1982

STP755-EB: Application of 2¼Cr-1 Mo Steel for Thick-Wall Pressure Vessels - 01 January 1982

STP28413S: A 2¼Cr-1Mo Pressure Vessel Steel with Improved Creep Rupture Strength - 01 January 1982

STP28414S: Data Obtained on Industrial Production Plates 150 to 500 mm (6 to 20 in.) Thick in Chromium-Molybdenum Steel - 01 January 1982

STP28415S: Effects of Composition and Heat Treatment on the Mechanical Properties of 300-mm-Gage 2¼Cr-1Mo Steel Plate - 01 January 1982

STP28416S: Structure and Mechanical Properties of 2¼Cr-1Mo Cast Steel for Pressure Components with Wall Thicknesses up to 500 mm - 01 January 1982

STP28417S: Mechanical Properties of Vacuum Carbon-Deoxidized Thick-Wall 2¼Cr-1Mo Steel Forging - 01 January 1982

STP28418S: Alloy Modification of Thick-Section 2¼Cr-1Mo Steel - 01 January 1982

STP28419S: Fabrication of Heavy-Wall Pressure Vessels - 01 January 1982

STP28408S: Internal Properties of 2¼Cr-1Mo Cast Steel for Heavy Castings - 01 January 1982

STP28420S: A Comparison of As-Welded and Stress-Relieved 2¼Cr-1Mo Steel Electroslag Weldments: Microstructure and Properties - 01 January 1982

STP28421S: A Portable 100-kW Electron Beam Welding System for Pressure Vessel Fabrication - 01 January 1982

STP28423S: Transformation Characteristics of 2¼Cr-1Mo Steel - 01 January 1982

STP28424S: Strength and Temper Embrittlement of Heavy-Section 2¼Cr-1Mo Steel - 01 January 1982

STP28425S: Heavy-Section 2¼Cr-1Mo Steel for Hydrogenation Reactors - 01 January 1982

STP28426S: Omission of Intermediate Postweld Heat Treatment (PWHT) by Utilizing Low-Temperature PWHT for Welds in Pressure Vessels - 01 January 1982

STP28427S: Comparison of Peened versus Postweld Heat-Treated Chromium-Molybdenum Alloy Steel Weldments - 01 January 1982

STP28428S: Summary - 01 January 1982

STP28409S: Fatigue Crack Propagation Behavior of 2¼Cr-1Mo Steels for Thick-Wall Pressure Vessels - 01 January 1982

STP28410S: Design Properties for Steels Used in Coal Conversion Vessels - 01 January 1982

STP28406S: Pressure Vessels for Coal Liquefaction—An Overview - 01 January 1982

STP28411S: Hydrogen Attack in Thick-Section 2¼Cr-1Mo Steels at Elevated Temperatures - 01 January 1982

STP28449S: Metallurgical Characteristics of a Large Hydraulic Runner Casting of Type 13Cr-Ni Stainless Steel - 01 January 1982

STP28438S: Production and Properties of Valve Bodies Made of Stabilized Chromium-Nickel Steel Castings for the Charge in Nuclear Power Stations - 01 January 1982

STP28853S: Applications of Fatigue and Fracture Tolerant Design Concepts in the Nuclear Power Industry - 01 January 1982

STP28898S: Multiaxial Creep of Textured Zircaloy-4 - 01 January 1982

STP32431S: Effect of Discontinuities on Low-Cycle Fatigue Behavior of NiMoV Rotor Forging Steel - 01 January 1982

STP32434S: Low-Cycle Fatigue Behavior of Thick High-Strength Steel Plates for Pressure Vessels - 01 January 1982

STP32441S: Effect of Light-Water Reactor Environments on Fatigue Crack Growth Rate in Reactor Pressure Vessel Steels - 01 January 1982

STP32447S: Use of Low-Cycle Fatigue Data for Pressure Vessel Design - 01 January 1982

STP32448S: Materials-Data Needs for Fatigue Design of Pressure Vessel Systems - 01 January 1982

STP36147S: Evaluation of Powder-Processed Metals for Turbine Engine Ball Bearings - 01 January 1982

STP32454S: Aggregate-Related Applications for Residues from Fluidized Bed Combustion Boilers - 01 January 1982

STP29397S: Fretting of Electrical Contacts - 01 January 1982

STP29398S: Heat Exchanger Tube Fretting Wear: Correlation of Tube Motion and Wear - 01 January 1982

STP34394S: Effect of Radiation-Induced Segregation on Void Nucleation - 01 January 1982

STP782-EB: Effects of Radiation on Materials - 01 January 1982

STP34395S: On Radiation-Induced Segregation and the Compositional Dependence of Swelling in Fe-Ni-Cr Alloys - 01 January 1982

STP34396S: Calculation of Cavity Nucleation Under Irradiation with Continuous Helium Generation - 01 January 1982

STP34397S: Hardening of Irradiated Alloys due to the Simultaneous Formation of Vacancy and Interstitial Loops - 01 January 1982

STP34398S: A Model for the Evolution of Network Dislocation Density in Irradiated Metals - 01 January 1982

STP34399S: Asymmetric Dislocation/Point-Defect Interactions and the Modeling of Void Swelling - 01 January 1982

STP34341S: An In-Reactor Creep Correlation for 20% Cold Worked AISI 316 Stainless Steel - 01 January 1982

STP34400S: Cooperative Effects in Microstructural Evolutions Under Irradiation: Fundamental Aspects - 01 January 1982

STP34401S: Three Mile Island-2: Influence on Commercial Nuclear Power Development - 01 January 1982

STP34402S: The European Fusion Materials Programme - 01 January 1982

STP34403S: Fusion Materials Development in the U.S. - 01 January 1982

STP34404S: Rapsodie and Phenix — The Materials Story - 01 January 1982

STP34405S: The U.K. Fast Reactor Materials Programme - 01 January 1982

STP34342S: Analysis of the High Fluence Creep Behavior of Two Precipitation Strengthened Alloys - 01 January 1982

STP34343S: Microstructural Changes in Neutron-Irradiated Commercial Alloys: A Sequel - 01 January 1982

STP34344S: The Influence of Cold Work Level, Solute and Helium Content on the Swelling of “Pure” AISI 316 (Fe-17Cr-16.7Ni-2.5Mo) - 01 January 1982

STP34345S: Precipitation in Irradiated and Unirradiated Austenitic Steels - 01 January 1982

STP34336S: The Swelling Behavior of 20% CW 316 Stainless Steel Cladding Irradiated With and Without Adjacent Fuel - 01 January 1982

STP34346S: Relationship Between Phase Development and Swelling of AISI 316 During Temperature Changes - 01 January 1982

STP34347S: Microstructural Stability of Fast Reactor Irradiated 10–12%Cr Ferritic-Martensitic Stainless Steels - 01 January 1982

STP34348S: Dislocation Substructure in Zirconium Alloys Irradiated in EBR-II - 01 January 1982

STP34349S: The Effect of Preimplanted Helium on the Microstructure of Neutron Irradiated Nb, Nb-1%Zr and Nb-1%Zr-0.4%Mo - 01 January 1982

STP34350S: Swelling in Neutron Irradiated Titanium Alloys - 01 January 1982

STP34351S: The Effect of Helium on Swelling in Stainless Steel: Influence of Cavity Density and Morphology - 01 January 1982

STP34352S: History Dependence and Consequences of the Microchemical Evolution of AISI 316 - 01 January 1982

STP34337S: Interdependence of In-Pile Creep and Void Swelling in Ti- and Nb-Stabilized Stainless Steels - 01 January 1982

STP34353S: Influence of Dose and Dose Rate Ont the Microstructure of Solution Annealed 316 Steel Irradiated Around 600 °C - 01 January 1982

STP34354S: Microstructure and Tensile Properties of Neutron-Irradiated (Fe0.61Ni0.39)3V Ordered Alloy - 01 January 1982

STP34355S: The Influence of Neutron Exposure, Chemical Composition and Metallurgical Condition, on the Irradiation Shift of Reactor Pressure Vessel Steels - 01 January 1982

STP34356S: Significance of Nickel and Copper Content to Radiation Sensitivity and Postirradiation Heat Treatment Recovery of Reactor Vessel Steels - 01 January 1982

STP34357S: Radiation Embrittlement of PWR Reactor Vessel Weld Metals : Nickel and Copper Synergism Effects - 01 January 1982

STP34358S: Comparative Irradiation Study of Reactor Pressure-Vessel Steel Weld Metals - 01 January 1982

STP34359S: Evaluation of Advanced Reactor Pressure Vessel Steels Under Neutron Irradiation - 01 January 1982

STP34338S: Initial Results of Swelling and Irradiation Creep Interaction Testing - 01 January 1982

STP34360S: Analysis of Fracture Surfaces of Reactor Pressure-Vessel Steels - 01 January 1982

STP34361S: The Effect of Accelerated Irradiation on Fracture Behaviour - 01 January 1982

STP34362S: Analytic Predictions of Embrittlement of SA 533 B Pressure Vessel Steels - 01 January 1982

STP34363S: Kinetics of Annealing of Irradiated Surveillance Pressure Vessel Steel - 01 January 1982

STP34364S: Irradiation Experiments in the Testing Nuclear Power Plant Vak - 01 January 1982

STP34365S: Effects of Neutron Irradiation and Temperature on High Strain Rate Behaviour of Reactor Pressure Vessel Steel - 01 January 1982

STP34366S: A Single Specimen Method for Determining Upper Shelf Fracture Toughness Shifts Using Precracked Charpy Specimens - 01 January 1982

STP34367S: Preparation of Reconstituted Charpy V-Notch Impact Specimens for Generating Pressure Vessel Steel Fracture Toughness Data - 01 January 1982

STP34368S: Low Dose Irradiation Effects of Heat-to-Heat Variation of Type 304 Stainless Steel Creep and Tensile Properties - 01 January 1982

STP34335S: The Swelling of Solution Annealed 316 Cladding in Rapsodie and Phenix - 01 January 1982

STP34369S: Irradiation Embrittlement in Some Austenitic Superalloys - 01 January 1982

STP34370S: Mechanical Properties of Highly Irradiated 20 Percent Cold Worked Type 316 Stainless Steel - 01 January 1982

STP34371S: Nickel-Doped Ferritic (Martensitic) Steels for Fusion Reactor Irradiation Studies: Tempering Behavior and Unirradiated and Irradiated Tensile Properties - 01 January 1982

STP34372S: Effects of Temperature and Strain Rate on the Low Cycle Fatigue Properties of Neutron Irradiated Stainless Steel DIN 1.4948 - 01 January 1982

STP34373S: Deformation Microstructure Developed During Fatigue Crack Propagation in Type 316 Stainless Steel at 593°C - 01 January 1982

STP34374S: Effects of Fast Neutron Irradiation on the Fracture Behavior of Stainless Steel - 01 January 1982

STP34339S: Creep and Swelling of Type 348 Stainless Steel at Temperatures up to 700 K and Comparison with Fast Reactor Data - 01 January 1982

STP34375S: Fatigue Crack Growth of Low-Fluence Neutron-Irradiated Stainless Steel DIN 1.4948 - 01 January 1982

STP34376S: The Influence of Neutron Irradiation on the Properties of Beryllium - 01 January 1982

STP34377S: A Comparison of Transient-Heating Burst Test Results of Unirradiated and Irradiated Zircaloy-4 Fuel Rod Cladding - 01 January 1982

STP34378S: Effects of Neutron Irradiation on the Mechanical Properties of a 5154-0 Type Aluminum Alloy - 01 January 1982

STP34379S: On the Possibility of Using Amorphous Metals in High Radiation Environments - 01 January 1982

STP34380S: Annealing of Radiation Damaged Monazite - 01 January 1982

STP34381S: Void Swelling of Ferritic Alloys Bombarded with Nickel Ions - 01 January 1982

STP34382S: Void Swelling and Phase Stability in Different Heats of Cold-Drawn Type 1.4970 Stainless Steel After Heavy-Ion Irradiation - 01 January 1982

STP34383S: Irradiation Creep of Dilute Nickel Alloys - 01 January 1982

STP34384S: Optimization of Precipitation Hardened Fe-Ni-Cr Alloys Using Nickel Ion Bombardment Simulation Studies - 01 January 1982

STP34385S: Ion Damage in 316 Stainless Steel Over a Broad Dose Range - 01 January 1982

STP34386S: Surface Segregation in Concentrated Ni-Cu Alloys Under Irradiation - 01 January 1982

STP34387S: The Effect of Nitrogen on Void Swelling of Stainless Steel - 01 January 1982

STP34388S: Mechanical Properties of 800-MeV Proton-Irradiated Metals2 - 01 January 1982

STP34389S: Damage Profile In Ion-Bombarded Nickel and Stainless Steel - 01 January 1982

STP34340S: Effect of Preinjected Helium on Swelling and Microstructure of Neutron Irradiated Pressurized Tubes of Type 316 Stainless Steel - 01 January 1982

STP34390S: The Effect of Pulse Irradiation on Void Swelling of a “Pure” 316 Stainless Steel - 01 January 1982

STP34391S: Comparison of Neutron and Heavy-Ion Damage in a Single-Phase Austenite - 01 January 1982

STP34392S: Defect Production Rates by Electrons, Ions and Neutrons in Cubic Metals - 01 January 1982

STP34393S: Kinetics of Radiation-Induced Segregation in Ternary Alloys - 01 January 1982

STP27587S: In-Service Evaluation of Multifrequency/Multiparameter Eddy-Current Technology for the Inspection of PWR Steam-Generator Tubing - 01 January 1981

STP27590S: In-Service Inspection of Steam-Generator Tubing Using Multiple-Frequency Eddy-Current Techniques - 01 January 1981

STP27592S: Advanced Multifrequency Eddy-Current System for Steam-Generator Inspection - 01 January 1981

STP27605S: Automatic Detection, Classification, and Sizing of Steam-Generator Tubing Defects by Digital Signal Processing - 01 January 1981

STP28209S: Fatigue Crack Growth Rates of Irradiated Pressure Vessel Steels in Simulated Nuclear Coolant Environment - 01 January 1981

STP725-EB: Effects of Radiation on Materials - 01 January 1981

STP28210S: Significance of Radiation Effects in Solid Radioactive Waste - 01 January 1981

STP28211S: An Internally Consistent Model for Radiation-Induced Void Swelling - 01 January 1981

STP28212S: Radiation-Enhanced Diffusion in Face-Centered Cubic Materials - 01 January 1981

STP28213S: Positron Lifetime Studies of Electron-Irradiated Copper - 01 January 1981

STP28214S: Simulation of Short-Term Annealing of Displacement Cascades in Face-Centered Cubic Metals - 01 January 1981

STP28215S: High-Density Equation of State for Helium and Its Application to Bubbles in Solids - 01 January 1981

STP28203S: Radiation Embrittlement of a PWR Vessel Steel: Effects of Impurities and Nickel Content - 01 January 1981

STP28216S: Applications of the Theory of Cavity Growth to Dual-Ion Swelling Experiments - 01 January 1981

STP28217S: Ductility Loss of Ion-Irradiated Zircaloy-2 in Iodine Environment - 01 January 1981

STP28218S: Radiation Hardening in Neutron-Irradiated Molybdenum and Its Alloys - 01 January 1981

STP28219S: Fracture Resistance of HT-9 After Irradiation at Elevated Temperature - 01 January 1981

STP28220S: Tensile, Creep, and Fatigue Properties of Low-Fluence Neutron-Irradiated Welded Joints DIN 1.4948 - 01 January 1981

STP28221S: Mechanical and Physical Properties of Irradiated Type 348 Stainless Steel - 01 January 1981

STP28222S: Tensile Properties of Neutron-Irradiated Nimonic PE16 - 01 January 1981

STP28223S: Effects of Neutron Irradiation on Fatigue and Creep-Fatigue Crack Propagation in Type 316 Stainless Steel at 649°C - 01 January 1981

STP28224S: State Variable Description of 316 Stainless Steel Postirradiation Mechanical Properties - 01 January 1981

STP28204S: Correlation Between Microhardness, Tensile Properties, and Notch Ductility of Irradiated Ferritic Steels - 01 January 1981

STP28225S: A Microstructural Interpretation of the Fluence and Temperature Dependence of the Mechanical Properties of Irradiated AISI 316 - 01 January 1981

STP28226S: Coarse Slip Processes and Crack Propagation in Irradiated Stainless Steel - 01 January 1981

STP28227S: Dynamic Mechanical Properties of AISI 304L Irradiated to 2.2 dpa - 01 January 1981

STP28228S: Postirradiation Cladding Strength Under Biaxial Loading with an Increasing Temperature Ramp - 01 January 1981

STP28229S: Microstructural Development in Dual-Ion-Bombarded 316 Stainless Steel - 01 January 1981

STP28230S: Microchemical Evolution of Neutron-Irradiated Stainless Steel - 01 January 1981

STP28231S: Comparison of High-Fluence Swelling Behavior of Austenitic Stainless Steels - 01 January 1981

STP28205S: Irradiation Surveillance Program as Applied in Switzerland - 01 January 1981

STP28232S: Response to Annealing and Reirradiation of AISI 304L Stainless Steel Following Initial High-Dose Neutron Irradiation in EBR-II - 01 January 1981

STP28233S: Point-Defect Clustering in the Presence of Mobile Helium and Immobile Traps - 01 January 1981

STP28234S: Effects of Dose Rate on the Precipitate Distribution in an Ion-Irradiated Nickel-Aluminum Alloy - 01 January 1981

STP28235S: Swelling in Reactor-Conditioned Nickel-Ion Irradiated Nimonic PE16 - 01 January 1981

STP28236S: Gamma Prime Coarsening and Redistribution in Nimonic PE16 - 01 January 1981

STP28237S: Effect of Material Variables on the Irradiation Performance of Boron Carbide - 01 January 1981

STP28238S: A Microstructural Explanation for the Low Swelling of Ferritic Steels - 01 January 1981

STP28202S: Apparent Embrittlement Saturation and Radiation Mechanisms of Reactor Pressure Vessel Steels - 01 January 1981

STP28239S: Irradiation-Induced Precipitation in Binary Palladium-Refractory Metal Alloys - 01 January 1981

STP28240S: Void Swelling in Molybdenum Alloys In Situ Observed by a High-Voltage Electron Microscope - 01 January 1981

STP28206S: Experimental Investigation of Multicycle Irradiation and Annealing Effects on Notch Ductility of A533-B Weld Deposits - 01 January 1981

STP28241S: A Study of Radiation Damage Produced in Thinned Specimens of 316 Stainless Steel by Energetic Helium Ions - 01 January 1981

STP28242S: Helium Bubble Growth in Vanadium - 01 January 1981

STP28243S: Irradiated Materials Measurement Technology - 01 January 1981

STP28244S: Stress-Enhanced Swelling of Metals During Irradiation - 01 January 1981

STP28245S: Effect of Temperature Changes on Swelling and Creep of AISI 316 - 01 January 1981

STP28246S: Reduction of Irradiation-Induced Creep and Swelling in AISI 316 by Compositional Modifications - 01 January 1981

STP28247S: Frank Loop Formation in Irradiated Metals in Response to Applied and Internal Stresses - 01 January 1981

STP28207S: J-R Curve Characterization of A533-B Weld Metal with Irradiation and Postirradiation Annealing - 01 January 1981

STP28208S: Influence of Neutron Irradiation on Mechanical Properties of Steels Under Impulsive Loading - 01 January 1981

STP28062S: Use of Zirconium Heat Exchangers in the Viscose Rayon Process - 01 January 1981

STP28054S: Tube Sheet Alternatives for Reactive Metal Tubed Heat Exchangers - 01 January 1981

STP33424S: Fractographic and Microstructural Analysis of Stress-Corrosion Cracking of ASTM A533 Grade B Class 1 Plate and ASTM A508 Class 2 Forging in Pressurized Reactor-Grade Water at 93°C - 01 January 1981

STP29318S: Proof-Load Determination for Pressure Vessels Wound with Aramid Fiber - 01 January 1981

STP33458S: Detecting Acoustic Emission During Cyclic Crack Growth in Simulated BWR Environment - 01 January 1981

STP33465S: The Use of Fatigue Crack Growth Technology in Fracture Control Plans for Nuclear Components - 01 January 1981

STP27684S: Controlling Quality of Ferroalloys and Alloying Additives in the Manufacture of Nickel Alloys for Nuclear Applications - 01 January 1981

STP28280S: Recent Advances in Ion Chromatography - 01 January 1981

STP742-EB: Power Plant Instrumentation for Measurement of High-Purity Water Quality - 01 January 1981

STP28281S: In-Plant System for Continuous Low-Level Ion Measurement in Steam-Producing Water - 01 January 1981

STP28271S: Critical Overview of Power Station Sampling and Analysis of Water and Steam - 01 January 1981

STP28282S: High-Purity Water Quality Monitoring Based on Ion-Selective Electrode Technology - 01 January 1981

STP28283S: Evaluation of Power Plant Measurement of Sodium Ions in High-Purity Main Steam and Feedwater Utilizing In-Line Continuous Specific-Ion Electrodes - 01 January 1981

STP28284S: Use of On-Line Atomic Absorption in a Power Plant Environment - 01 January 1981

STP28285S: Zero: The Unreachable Goal - 01 January 1981

STP28286S: Resistivity of Very Pure Water and Its Maximum Value - 01 January 1981

STP28287S: Continuous Conductivity Monitoring of Anions in High-Purity Water - 01 January 1981

STP28288S: Description and Evaluation of a Continuous Sample Water Evaporator - 01 January 1981

STP28289S: Determination of Trace Chlorine and Oxidants in Seawater by Differential Pulse Polarography - 01 January 1981

STP28272S: A Consulting Engineer's Role in Power Plant Instrumentation for Measurement of High-Purity Water Quality - 01 January 1981

STP28273S: Power Plant Instrumentation for Measurement of High-Purity Water Quality - 01 January 1981

STP28274S: Status of Continuous Monitoring in Central Stations - 01 January 1981

STP28275S: Power Plant Water Quality Instrumentation: A Guideline for Operation, Calibration, and Maintenance - 01 January 1981

STP28276S: Program for Steam Purity Monitoring: 1. Instrumentation and Sampling - 01 January 1981

STP28277S: Program for Steam Purity Monitoring: 2. Results of Power Plant Testing - 01 January 1981

STP28278S: Quantification of Sodium, Chloride, and Sulfate Transport in Power-Generating Systems - 01 January 1981

STP28270S: Monitoring Power Plant Water Chemistry - 01 January 1981

STP28279S: Determination of Anions in High-Purity Water by Ion Chromatography - 01 January 1981

STP28362S: Microbiological Contamination of Fuels During Storage - 01 January 1981

STP36063S: NBS Solar Collector Durability/Reliability Program - 01 January 1980

STP35098S: The Need for Standards of Analysis in the Nuclear Power Industry - 01 January 1980

STP35099S: New Directions in Environmental Radiological Surveillance at Commonwealth Edison's Nuclear Stations - 01 January 1980

STP35100S: New England States Environmental Radiation Surveillance Programs - 01 January 1980

STP35101S: Present Practices and Future Requirements for Monitoring the Aquatic Environment at Nuclear Facilities - 01 January 1980

STP35102S: Analysis of Environmental Samples—Tennessee Valley Authority's Radiological Environmental Monitoring Program - 01 January 1980

STP35104S: Nuclear Regulatory Commission Region I Environmental Monitoring Inspection Program - 01 January 1980

STP35105S: The Role of Field Measurements in Environmental Radiation Monitoring - 01 January 1980

STP35107S: Acceptable Radiological Environmental Monitoring Programs: Nuclear Regulatory Commission Staff Rationale and Perspective - 01 January 1980

STP35108S: Confirmatory Measurements of Radionuclide Concentrations in Power Reactor Effluents - 01 January 1980

STP35109S: Preparations for High-Level Defense Waste Immobilization at Savannah River Plant - 01 January 1980

STP35110S: Migration of Radionuclides in Geologic Media—Laboratory and Field Studies - 01 January 1980

STP35111S: Experience with an Analytical Quality-Control Program - 01 January 1980

STP35112S: The Status and Quality of Radiation Measurements in Water—1977 - 01 January 1980

STP35113S: Quality Assurance for Effluent and Environmental Monitoring—A Nuclear Regulatory Commission Overview - 01 January 1980

STP35114S: The DOE-OES-EML Quality Assurance Program - 01 January 1980

STP35116S: Standards for the Assay of Radionuclides in Solid Environmental Samples - 01 January 1980

STP35091S: Discrepancies Between Film and Thermoluminescent Dosimetry (TLD) Readings at an Operating Power Reactor - 01 January 1980

STP35117S: Discordant Gross Radioactivity Measurements of Natural and Treated Waters - 01 January 1980

STP35118S: The Standardization of Alpha-Particle Sources - 01 January 1980

STP35092S: External and Internal Dosimetry—The Correlation Between Response and Dose Interpretation - 01 January 1980

STP35093S: Role of American Nuclear Insurers in Reducing Occupational Radiation Exposure - 01 January 1980

STP35094S: Composition and Measurement of Radionuclides in Liquid Effluent from Nuclear Power Stations - 01 January 1980

STP35095S: Radionuclides in Liquid Effluents from Argonne National Laboratory—An Example of Monitoring for a Multidisciplinary Nuclear Laboratory - 01 January 1980

STP35096S: Methodology for the Determination of Environmental 129I and 99Tc - 01 January 1980

STP35097S: Radiological Emergency Response Planning - 01 January 1980

STP38651S: In Situ AES and ESCA Analysis of Iron Oxides Formed by a Galvanic Cell - 01 January 1980

STP36977S: A Stability Analysis of Circumferential Cracks for Reactor Piping Systems - 01 January 1980

STP36980S: Temperature Dependence of the Fracture Toughness and the Cleavage Fracture Strength of a Pressure Vessel Steel - 01 January 1980

STP27454S: Fast Fracture Toughness and Crack Arrest Toughness of Reactor Pressure Vessel Steel - 01 January 1980

STP27460S: Crack Arrest in Water-Cooled Reactor Pressure Vessels During Loss-of-Coolant Accident Conditions - 01 January 1980

STP27467S: Corrosion of Steel Tendons Used in Prestressed Concrete Pressure Vessels - 01 January 1980

STP27485S: Effects of Gas Turbine Engine Load Spectrum Variables on Crack Propagation - 01 January 1980

STP27484S: Observation of Crack Retardation Resulting from Load Sequencing Characteristic of Military Gas Turbine Operation - 01 January 1980

STP27507S: Cold Neutron Imaging for Gas Turbine Inspection - 01 January 1980

STP30063S: Material Selection Guidelines for Geothermal Power Systems—An Overview - 01 January 1980

STP30065S: Corrosion Protection of Solar-Collector Heat Exchangers and Geothermal Systems by Electrodeposited Organic Films - 01 January 1980

STP35802S: Calculated Tolerance of a Large Electric Utility Gas Turbine to Erosion Damage by Coal Gas Ash Particles - 01 January 1979

STP38114S: Dynamic Straining Stress Corrosion Test for Predicting Boiling Water Reactor Materials Performance - 01 January 1979

STP38115S: Slow Strain-Rate Stress Corrosion Testing for Liquid Metal Fast Breeder Reactor Steam Generator Applications - 01 January 1979

STP35845S: Static and Dynamic Fibrous Initiation Toughness Results for Nine Pressure Vessel Materials - 01 January 1979

STP35852S: An Elastic-Plastic R-Curve Description of Fracture in Zr-2.5Nb Pressure Tube Alloy - 01 January 1979

STP37824S: Detection of Corona Discharges in Lumped Circuit Specimens - 01 January 1979

STP669-EB: Engineering Dielectrics Volume I Corona Measurement and Interpretation - 01 January 1979

STP37825S: Partial Discharge Measurements in Distributed Parameter Systems: Cables - 01 January 1979

STP37826S: Measurement of Partial Discharges in Inductive Apparatus: Transformers and Rotating Machines - 01 January 1979

STP37827S: Corona Endurance Tests - 01 January 1979

STP37822S: Corona Discharge Processes in Voids - 01 January 1979

STP37828S: Corona Measurements Using Bridge Methods - 01 January 1979

STP37829S: Corona Pulse Counting and Pulse-Height Analysis Techniques - 01 January 1979

STP37830S: Acoustical Techniques for Detecting and Locating Electrical Discharges - 01 January 1979

STP37821S: Some General Remarks on Corona Discharges - 01 January 1979

STP37831S: Partial Discharges Under Direct-Voltage Conditions - 01 January 1979

STP37832S: Partial Discharges Under Impulse-Voltage Conditions - 01 January 1979

STP37823S: Fundamentals of Partial-Discharge Detection: System Sensitivity and Calibration - 01 January 1979

STP36616S: Design of High Hardness, Tough Steels for Energy-Related Applications - 01 January 1979

STP36886S: Microstructural Objectives for High-Temperature Alloys in Advanced Energy Systems - 01 January 1979

STP34910S: Effects of Temperature and Frequency on the Fatigue Crack Growth Rate Properties of a 1950 Vintage CrMoV Rotor Material - 01 January 1979

STP38356S: Development of Austenitic Stainless Steels with Controlled Residual Nitrogen Content; Application to Nuclear Energy - 01 January 1979

STP36675S: Further Evidence of Zircaloy Corrosion in Fuel Elements Irradiated in a Steam Generating Heavy Water Reactor - 01 January 1979

STP36676S: Performance of Irradiated Copper and Zirconium Barrier-Modified Zircaloy Cladding Under Simulated Pellet-Cladding Interaction Conditions - 01 January 1979

STP36677S: A Survey of the Chemical Environments for Activity in the Embrittlement of Zircaloy-2 - 01 January 1979

STP36678S: Effect of Irradiation on the Strength, Ductility, and Defect Sensitivity of Fully Recrystallized Zircaloy Tube - 01 January 1979

STP36679S: Primary Creep of Zircaloy-2 Under Irradiation - 01 January 1979

STP36680S: Analysis of Irradiation Growth and Multiaxial Deformation Behavior of Nuclear Fuel Cladding - 01 January 1979

STP36670S: Zircaloy Performance in Light-Water Reactors - 01 January 1979

STP36681S: Analysis of Pressurized Water Reactor Fuel Pin Length Changes - 01 January 1979

STP36682S: Irradiation Growth in Cold-Worked Zircaloy-2 - 01 January 1979

STP36683S: Stress Corrosion Crack Initiation and Growth and Formation of Pellet-Clad Interaction Defects - 01 January 1979

STP36684S: Out-of-Pile Testing of Iodine Stress Corrosion Cracking in Zircaloy Tubing in Relation to the Pellet-Cladding Interaction Phenomenon - 01 January 1979

STP36685S: Iodine-Induced Stress Corrosion Cracking of Fixed Deflection Stressed Slotted Rings of Zircaloy Fuel Cladding - 01 January 1979

STP36686S: A Stress Corrosion Cracking Model for Pellet-Cladding Interaction Failures in Light-Water Reactor Fuel Rods - 01 January 1979

STP36687S: Hydride Cracks as Initiators for Stress Corrosion Cracking of Zircaloys - 01 January 1979

STP36688S: Predicting High-Temperature Transient Deformation from Microstructural Models - 01 January 1979

STP36689S: A Microstructure-Based Constitutive Relation for Dilute Alloys of α-Zirconium - 01 January 1979

STP36690S: A Comparison of Experimental Cladding Microstructure Resulting from Uranium Oxide-Zircaloy Interaction with a Diffusional Assessment of Oxygen Transport for a Coupled Two-Media Problem - 01 January 1979

STP36691S: Advances in Understanding and Predicting Inelastic Deformation in Zircaloy - 01 January 1979

STP36692S: Zirconium Cladding Deformation in a Steam Environment with Transient Heating - 01 January 1979

STP36693S: Influence of Iodine on the Strain and Rupture Behavior of Zircaloy-4 Cladding Tubes at High Temperatures - 01 January 1979

STP36671S: Effect of Material and Environmental Variables on Localized Corrosion of Zirconium Alloys - 01 January 1979

STP36694S: Studies on Zircaloy Fuel Clad Ballooning in a Loss-of-Coolant Accident—Results of Burst Tests with Indirectly Heated Fuel Rod Simulators - 01 January 1979

STP36695S: Effect of β-Phase Heat Treatment on the Subsequent α-Phase Ballooning Behavior of Zircaloy-4 Fuel Sheaths - 01 January 1979

STP36696S: Tube-Burst Response of Irradiated Zircaloy Spent-Fuel Cladding - 01 January 1979

STP36697S: A Proposed Criterion for the Oxygen Embrittlement of Zircaloy-4 Fuel Cladding - 01 January 1979

STP36698S: Effect of Oxygen on the Deformation of Zircaloy-2 at Elevated Temperatures - 01 January 1979

STP36699S: Evaluation Models of Zircaloy Oxidation in Light of Recent Experiments - 01 January 1979

STP36700S: Chemical Interaction Between Uranium Oxide and Zircaloy-4 in the Temperature Range Between 900 and 1500°C - 01 January 1979

STP36701S: Interaction of Oxidation and Creep in Zircaloy-2 - 01 January 1979

STP36702S: Embrittlement of Zircaloy-Clad Fuel Rods Irradiated Under Film Boiling Conditions - 01 January 1979

STP36669S: Zirconium Technology—Twenty Years of Evolution - 01 January 1979

STP36703S: Development of an Oxygen Embrittlement Criterion for Zircaloy Cladding Applicable to Loss-of-Coolant Accident Conditions in Light-Water Reactors - 01 January 1979

STP36672S: Ductility of Zircaloy Canning Tubes in Relation to Stress Ratio in Biaxial Testing - 01 January 1979

STP36673S: Localized Ductility Method for Evaluating Zircaloy-2 Cladding - 01 January 1979

STP36674S: Review of Corrosion and Dimensional Behavior of Zircaloy under Water Reactor Conditions - 01 January 1979

STP38161S: Effects of Neutron Irradiation on the Microstructure of Niobium and Niobium-Base Alloys - 01 January 1979

STP683-EB: Effects of Radiation on Structural Materials - 01 January 1979

STP38162S: Effects of Bombarding Ions on the Void Swelling Profile in Nickel - 01 January 1979

STP38155S: Radiation Effects on Molybdenum Alloys Bombarded by Electrons in a High-Voltage Electron Microscope - 01 January 1979

STP38163S: Development of Physically Based Void Swelling Equations for Engineering and Design Use - 01 January 1979

STP38164S: A Reassessment of the Role of Stress in Development of Radiation-Induced Microstructure - 01 January 1979

STP38165S: Radiation-Induced Segregation in Nickel-Silicon Alloys - 01 January 1979

STP38166S: An Example of Precipitate Stability in Reactor-Irradiated Nimonic PE16 - 01 January 1979

STP38167S: Dependence of Void Formation on Phase Stability in Neutron-Irradiated Type 316 Stainless Steel - 01 January 1979

STP38168S: Evaluation of Commercial Production A533-B Steel Plates and Weld Deposits with Extra-Low Copper Content for Radiation Resistance - 01 January 1979

STP38169S: An Empirical Evaluation of the Irradiation Sensitivity of Reactor Pressure Vessel Materials - 01 January 1979

STP38170S: Irradiation Behavior of Nickel-Chromium-Molybdenum Type Weld Metal - 01 January 1979

STP38171S: Exploratory Investigations of Cyclic Irradiation and Annealing Effects on Notch Ductility of A533-B Weld Deposits - 01 January 1979

STP38172S: Effect and Possibilities of Irradiation Results Error Correction (Demonstrated on the Results of the IAEA Coordinated Program) - 01 January 1979

STP38173S: Fracture Toughness of Irradiated Beryllium - 01 January 1979

STP38174S: Irradiation Creep and Growth in Zirconium During Proton Bombardment - 01 January 1979

STP38156S: Microstructural Development During Low-Dose Irradiation - 01 January 1979

STP38175S: Radiation Damage Effects in 16-MeV Proton and 14-MeV Neutron Irradiated Nickel and Niobium - 01 January 1979

STP38176S: Helium Production in Fast Breeder Reactor Out-of-Core Structural Components - 01 January 1979

STP38177S: Radiation Damage Function Analysis - 01 January 1979

STP38178S: Solid-State Track Recorder Materials for Use in Light-Water-Reactor Pressure Vessel Surveillance Exposures - 01 January 1979

STP38179S: Microstructure and Tensile Properties of Heavily Irradiated 1100-0 Aluminum - 01 January 1979

STP38180S: Tensile Properties of Neutron-Irradiated 6061 Aluminum Alloy in Annealed and Precipitation-Hardened Conditions - 01 January 1979

STP38181S: Tensile Property Correlations for Highly Irradiated 20 Percent Cold-Worked Type 316 Stainless Steel - 01 January 1979

STP38182S: Low-Cycle Fatigue of Three Irradiated and Unirradiated Vanstar Alloys - 01 January 1979

STP38157S: Neutron Irradiation-Induced Defect Structures in Zirconium - 01 January 1979

STP38183S: Effects of Neutron Irradiation and Fatigue on Ductility of Stainless Steel DIN 1.4948 - 01 January 1979

STP38184S: Estimates of Time-Dependent Fatigue Behavior of Type 316 Stainless Steel Subject to Irradiation Damage in Fast Breeder and Fusion Power Reactor Systems - 01 January 1979

STP38185S: Fracture Toughness of Irradiated AISI 304 and 316L Stainless Steels - 01 January 1979

STP38186S: Fracture Toughness of Irradiated Nimonic PE16 at High Temperatures - 01 January 1979

STP38187S: Effects of Irradiation on the Mechanical Properties of Austenitic Stainless Steels Under Dynamic Loading - 01 January 1979

STP38188S: Effects of Irradiation Temperature, Fluence, and Heating Rate on Postirradiation Flow Properties of Cladding Under Simulated Temperature Transient Heating and Deformation Conditions - 01 January 1979

STP38189S: Effects of Irradiation Creep on Ex-Reactor Mechanical Properties - 01 January 1979

STP38190S: Formulation of Constitutive Laws for Deformation During Irradiation - 01 January 1979

STP38191S: Irradiation Creep in Bending of Cold-Worked AISI 316 Stainless Steel at Low Neutron Fluence - 01 January 1979

STP38154S: Determination of the Nature of Neutron Irradiation-Induced Dislocation Loops in Magnesium Using Electron Irradiation in the Transmission Electron Microscope - 01 January 1979

STP38192S: A Comparison of Fuel Pin Deformations with Pressurized Tube Creep Tests - 01 January 1979

STP38193S: Reduction of Irradiation-Induced Creep by Point-Defect Trapping - 01 January 1979

STP38158S: Irradiation Growth in Zirconium and Its Alloys - 01 January 1979

STP38194S: Irradiation Creep Due to Stress-Induced Preferred Absorption of Point Defects in Zirconium Single Crystals - 01 January 1979

STP38195S: In-Reactor Deformation and Fracture of Austenitic Stainless Steels - 01 January 1979

STP38159S: Dependence of Cavity Nucleation Density Upon Gas Implantation Rate and Its Importance in Dual-Beam Irradiation Conditions - 01 January 1979

STP38160S: Response of Inconel 600 to Simulated Fusion Reactor Irradiation - 01 January 1979

STP35079S: Acoustic Emission Measurements: HSST V-7B Intermediate Vessel Test - 01 January 1979

STP35081S: Inspection of Nuclear Reactors by Means of Acoustic Emission during Hydrostatic Test - 01 January 1979

STP35082S: Experience with the Acoustic Emission Monitoring of a Steam Drum Nozzle in a CANdu Nuclear Generating Station - 01 January 1979

STP35083S: Acoustic Monitoring for Leak Detection in Pressurized Water Reactors - 01 January 1979

STP35084S: Acoustic Emission Surveillance of Boiling Water Reactor Piping Nozzles and Valves - 01 January 1979

STP35078S: Acoustic Emission Monitoring of Intermediate Pressure Vessels Tested under the ORNL Heavy Section Steel Technology Program - 01 January 1979

STP38095S: Fractographic Analysis of Low Cycle Fatigue Specimens from a Failed Steam Turbine Rotor - 01 January 1978

STP38097S: Examination of Fracture in a Pressure Vessel under Creep Conditions - 01 January 1978

STP27313S: Effects of Air Pollutants on Weathering Steel and Galvanized Steel: A Chamber Study - 01 January 1978

STP33397S: Elevated Temperature Fatigue Characterization of Transition Joint Weld Metal and Heat Affected Zone in Support of Breeder Steam Generator Development - 01 January 1978

STP34843S: Intergranular Corrosion in Nuclear Systems - 01 January 1978

STP27918S: Chapter 7—Cause and Effects Analysis - 01 January 1977

STP616-EB: Quality Systems in the Nuclear Industry - 01 January 1977

STP27919S: Chapter 8—Consequence Analysis - 01 January 1977

STP27920S: Chapter 9—Component/Part Application Analysis - 01 January 1977

STP27921S: Chapter 10—Maintenance and Spares Analyses - 01 January 1977

STP27922S: Chapter II—Design Review - 01 January 1977

STP27923S: Chapter 12—Quality Requirements for Supplies - 01 January 1977

STP27912S: Chapter 1—Meanings, Goals, and Scope of Quality - 01 January 1977

STP27924S: Chapter 13—Source Selection - 01 January 1977

STP27925S: Chapter 14—Measurement Control - 01 January 1977

STP27913S: Chapter 2—The Systems Approach - 01 January 1977

STP27926S: Chapter 15—Component Qualification - 01 January 1977

STP27927S: Chapter 16—Design Change Control - 01 January 1977

STP27928S: Chapter 17—Acceptance Sampling - 01 January 1977

STP27929S: Chapter 18—Inspection/Test Planning and Process Control - 01 January 1977

STP27914S: Chapter 3—The Product Evolution Cycle - 01 January 1977

STP27930S: Chapter 19—Control of Noncomforming Items - 01 January 1977

STP27915S: Chapter 4—Requirements Type Documents - 01 January 1977

STP27932S: Chapter 21—Quality Information Feedback and Corrective Action - 01 January 1977

STP27933S: Chapter 22—Auditing Quality Systems and Inspection Effectiveness - 01 January 1977

STP27934S: Chapter 23—Industrial Psychology in Quality Control - 01 January 1977

STP27935S: Chapter 24—Economics of Quality - 01 January 1977

STP27916S: Chapter 5—Design Requirements - 01 January 1977

STP27917S: Chapter 6—Tolerancing - 01 January 1977

STP27013S: Nondestructive Testing Standards in the ASME Boiler and Pressure Vessel Code - 01 January 1977

STP27015S: Codes and Standards for In-Service Inspection of Nuclear Power Plants - 01 January 1977

STP35557S: Prediction of Fracture Toughness KIc of 2¼Cr-1Mo Pressure Steels from Charpy V-Notch Test Results - 01 January 1977

STP35568S: Diffusion of Oxygen in Beta-Zircaloy and the High Temperature Zircaloy-Steam Reaction - 01 January 1977

STP35570S: Zircaloy-4 Oxidation in Steam Under Transient Oxidizing Conditions - 01 January 1977

STP35572S: Zircaloy Cladding Behavior During Irradiation Tests Under Power-Cooling-Mismatch Conditions - 01 January 1977

STP35574S: Nodular Corrosion of Zircaloy-2 and Some Other Zirconium Alloys in Steam Generating Heavy Water Reactors and Related Environments - 01 January 1977

STP35562S: Diameter Increases in Steam Generating Heavy Water Reactor Zircaloy Cans under Loss-of-Coolant Accident Conditions - 01 January 1977

STP35575S: Corrosion Monitoring of Steam Generating Heavy Water Reactor Pressure Tubes - 01 January 1977

STP35576S: Embrittlement of Zircaloy-4 by Liquid Cesium at 300°C - 01 January 1977

STP35577S: Nodular Corrosion of the Zircaloys - 01 January 1977

STP35578S: Use of State Variables in the Description of Irradiation Creep and Deformation of Metals - 01 January 1977

STP35579S: Irradiation Growth of Zircaloy - 01 January 1977

STP35580S: Zircaloy-2 Pressure Tube Elongation at the Hanford N Reactor - 01 January 1977

STP35581S: Numerical Model for the Anisotropic Creep of Zircaloy - 01 January 1977

STP35563S: Rupture Characteristics of Zircaloy-4 Cladding with Internal and External Simulation of Reactor Heating - 01 January 1977

STP35582S: Modeling of Localized Deformation in Neutron Irradiated Zircaloy-2 - 01 January 1977

STP35583S: In-Reactor Creep of Zr-2.5Nb Fuel Cladding - 01 January 1977

STP35584S: Effect of Stress on Radiation Damage in Neutron Irradiated Zirconium Alloys - 01 January 1977

STP35585S: Irradiation Response of the Ordered Phase Zr3Al - 01 January 1977

STP35586S: Fabrication of Zirconium Alloys into Components for Nuclear Reactors - 01 January 1977

STP35587S: Mechanical Properties, Anisotropy, and Microstructure of Zircaloy Canning Tubes - 01 January 1977

STP35588S: Yield and Fracture of Biaxially Stressed Zircaloy-4 Cladding Tubes at Room Temperature and at 400°C - 01 January 1977

STP35564S: High Temperature Strain Behavior of Zircaloy-4 and Zr-2.5Nb Fuel Sheaths - 01 January 1977

STP35589S: Progress in Modeling of Zircaloy Nonelastic Deformation Using a Unified Phenomenological Model - 01 January 1977

STP35590S: Fracture of Zircaloy Cladding by Interactions with Uranium-Dioxide Pellets in Water Reactor Fuel Rods - 01 January 1977

STP35591S: Localized Ductility of Irradiated Zircaloy-2 Cladding in Air and Iodine Environments - 01 January 1977

STP35592S: Acoustic Emission during Room Temperature Fatigue Crack Growth and Fracture of Zr-2.5Cb Alloy Specimens - 01 January 1977

STP35561S: Zircaloy—Three Years after the Hearings - 01 January 1977

STP35597S: Standardization Works on Testing Procedures for Zircaloy Cladding Tubes in Japan - 01 January 1977

STP35565S: Superplasticity of Zircaloy-4 - 01 January 1977

STP35566S: Deformation and Rupture Behavior of Zircaloy Cladding under Simulated Loss-of-Coolant Accident Conditions - 01 January 1977

STP35567S: Influence of Metallurgical Variables on the Performance of Zircaloy Fuel Sheathing - 01 January 1977

STP36570S: Corrosion Rate Monitoring in Gas and Oil Production - 01 January 1977

STP42070S: Chapter 7—Heating and Power Generation Fuels - 01 January 1977

STP41398S: Galvanic Corrosion of Underground Power Distribution Cable Materials - 01 January 1976

STP33919S: Neutron Radiography to Detect Residual Core in Investment Cast Turbine Airfoils - 01 January 1976

STP33922S: Neutron Radiography of Nuclear Fuels at the Battelle Research Reactor - 01 January 1976

STP33923S: Detecting Cladding Leaks in Irradiated Fuel Elements by Neutron Radiography - 01 January 1976

STP33924S: Neutron Radiography of Fuel Pins - 01 January 1976

STP33925S: Nuclear Applications of Neutron Radiography and Gaging - 01 January 1976

STP33958S: Stress Intensity Factor Solutions for Continuous Surface Flaws in Reactor Pressure Vessels - 01 January 1976

STP32370S: A Calibration Procedural System and Facility for Gas Turbine Engine Exhaust Emission Analysis - 01 January 1976

STP28651S: Preliminary Results of a Program for Developing Fracture Toughness Data on Ferritic Nuclear Pressure Vessel Steels - 01 January 1976

STP38043S: Mechanical Properties of Fast Reactor Fuel Cladding for Transient Analysis - 01 January 1976

STP611-EB: Irradiation Effects on The Microstructure and Properties of Metals - 01 January 1976

STP38044S: Tensile Properties of Fast Reactor Irradiated Type 304 Stainless Steel - 01 January 1976

STP38045S: Effects of Neutron Irradiation on Microstructure and Mechanical Properties of Nimonic PE-16 - 01 January 1976

STP38046S: Irradiation and Thermal Effects on the Tensile Properties of Inconel-718 - 01 January 1976

STP38047S: Tensile and Hardness Property Evaluations of Irradiated Zircaloy Cladding Under Off-Normal and Transient Conditions - 01 January 1976

STP38048S: Neutron Energy Dependent Damage Functions for Tensile Properties of 20 Percent Cold-Worked Type 316 Stainless Steel - 01 January 1976

STP38049S: Swelling Simulation Studies of Type 316 Stainless Steel - 01 January 1976

STP38050S: Development and Evaluation of a Stress-Free Swelling Correlation for 20 Percent Cold-Worked Type 316 Stainless Steel - 01 January 1976

STP38051S: Swelling Behavior of Commercial Ferritic Alloys, EM-12 and HT-9, as Assessed by Heavy Ion Bombardment - 01 January 1976

STP38052S: Observation of Defect Clusters of Columbium and Columbium Alloys In Situ Irradiated Under a High-Voltage Electron Microscope - 01 January 1976

STP38053S: Void Growth Suppression by Dislocation Impurity Atmospheres - 01 January 1976

STP38054S: Dependence of Void Swelling on the Electron Vacancy Concentration - 01 January 1976

STP38055S: Microstructure and Mechanisms of Ion-Simulated Irradiation-Induced Creep of Nickel - 01 January 1976

STP38056S: Effects of Interstitial Solutes on the Microstructures of Self-Ion Irradiated Vanadium - 01 January 1976

STP38057S: Swelling and Gamma-Prime Particle Stability of Ion-Bombarded Iron-Chromium-Nickel Alloys - 01 January 1976

STP38039S: Analysis of In-Reactor Stress Relaxation Using Irradiation Creep Models - 01 January 1976

STP38058S: Effect of Ion Irradiation on the Microstructure of an Iron-Nickel-Chromium Alloy - 01 January 1976

STP38059S: Microstructural Changes in Ion-Irradiated Commercial Alloys - 01 January 1976

STP38060S: Nickel-Ion Damage in a Precipitation-Hardened Nickel-Aluminum - 01 January 1976

STP38061S: Fracture Mechanics Characterization of the Trino Reactor Vessel Material - 01 January 1976

STP38062S: Evaluation of the Maine Yankee Reactor Beltline Materials - 01 January 1976

STP38063S: Evaluation of the Effect of Chemical Composition on the Irradiation Sensitivity of Reactor Vessel Weld Metal - 01 January 1976

STP38064S: Annealing of Irradiation Damage in High-Copper Ferritic Steels - 01 January 1976

STP38065S: Displacement Spike Annealing in Iron at Reactor Temperatures - 01 January 1976

STP38066S: Neutron Displacement Damage Cross Sections for Structural Metals - 01 January 1976

STP38040S: Dynamic Strain-Aging and Neutron Irradiation in Mild Steel - 01 January 1976

STP38038S: Effects of Prior Stress History on Irradiation-Induced Creep - 01 January 1976

STP38041S: Swelling and Tensile Property Changes in Neutron-Irradiated Type 316 Stainless Steel - 01 January 1976

STP38042S: Effect of Fast Reactor Irradiation on the Tensile Properties of 20 Percent Cold-Worked Type 316 Stainless Steel - 01 January 1976

STP27889S: Some Thermal Fatigue Characteristics of Mild Steel for Heat Exchangers - 01 January 1976

STP570-EB: Properties of Reactor Structural Alloys After Neutron or Particle Irradiation - 01 January 1975

STP33681S: Effect of Impurity Concentration on the Change in Fracture Toughness of AISI Type 403 Stainless Steel with Fast Neutron Radiation - 01 January 1975

STP33682S: Radiation Damage and Fatigue Evaluation of Reactor End Fittings - 01 January 1975

STP33683S: Effect of Irradiation at 130, 650, and 775°F on Tensile Properties of Zircaloy-4 at 70, 650, and 775°F - 01 January 1975

STP33684S: Effect of Neutron Irradiation on Types 316 and 321 and Sandvik 12R72 Stainless Steels - 01 January 1975

STP33685S: Fatigue Behavior and Microstructure of Neutron Irradiated Thin Section Type 304 Stainless Steel at Elevated Temperatures - 01 January 1975

STP33686S: Fatigue and Creep-Fatigue Behavior of Irradiated and Unirradiated Type 308 Stainless Steel Weld Metal at Elevated Temperatures - 01 January 1975

STP33687S: Fatigue Crack Propagation in Fast Neutron Irradiated Stainless Steels and Welds - 01 January 1975

STP33688S: Dose Dependence of Irradiation Creep of Zircaloy-2 - 01 January 1975

STP33689S: Improvement of Creep Properties in a Helium Injected Austenitic Stainless Steel - 01 January 1975

STP33690S: Creep and Swelling Deformation in Structural Materials During Fast-Neutron Irradiation - 01 January 1975

STP33674S: Decrease of Ductility Upon Neutron Irradiation in Iron Alloys and Columbium - 01 January 1975

STP33691S: Multiaxial Primary Irradiation Creep Equations for Reactor Structural Materials - 01 January 1975

STP33692S: Surface Reaction Limited Void Growth - 01 January 1975

STP33693S: Spectral Effects in Neutron and Charged Particle Irradiations - 01 January 1975

STP33695S: Postirradiation Properties of the 6061-T6 Aluminum High Flux Isotope Reactor Hydraulic Tube - 01 January 1975

STP33696S: Comparison of Displacement and Gas Production Rates in Current Fission and Future Fusion Reactors - 01 January 1975

STP33697S: Helium Mobility and Bubble Formation in Type 316 Stainless Steel, Aluminum, and Vanadium - 01 January 1975

STP33699S: Irradiation-Induced Swelling Variations Resulting from Compositional Modifications of Type 316 Stainless Steel - 01 January 1975

STP33701S: Effect of the Degree of Cold Work on the Irradiation-Induced Swelling of Type 316 Stainless Steel - 01 January 1975

STP33675S: Interaction of Strain and Radiation Damages in a Pressure Vessel Steel - 01 January 1975

STP33702S: Dimensional Stability of Neutron Irradiated Molybdenum - 01 January 1975

STP33704S: Dimensional Stability of Tantalum During Fast Neutron Irradiation - 01 January 1975

STP33705S: Influence of High Voltage Electron Microscope Irradiation on Neutron-Produced Microstructures in Stainless Steels - 01 January 1975

STP33707S: Swelling in Electron-Irradiated Type 316 Stainless Steel - 01 January 1975

STP33709S: Void Formation in Cold-Worked Type 316 Stainless Steel Irradiated with 1-MeV Protons - 01 January 1975

STP33710S: Void Formation in an Ion Bombarded Cold-Worked Stainless Steel - 01 January 1975

STP33711S: Effect of Irradiation Parameters on Nickel-Ion Damage in Nickel - 01 January 1975

STP33712S: Void Swelling in the Iron-Chromium-Nickel System—A Survey by Nickel Ion Bombardment - 01 January 1975

STP33713S: Swelling Resistance Induced by Grain Refinement and Particle Dispersion in Austenitic Stainless Steel During High Energy Electron Irradiation - 01 January 1975

STP33676S: Strength and Notch Ductility of Selected Structural Alloys After High Fluence 550°F (288°C) Irradiation - 01 January 1975

STP33714S: Development Programs on Irradiation Embrittlement of Low Alloy Pressure Vessel Steels in the Federal Republic of Germany - 01 January 1975

STP33715S: Swelling and Irradiation Induced Microstructural Changes in Nickel-Based Alloys - 01 January 1975

STP33716S: Irradiated Steels Behavior in Long-Term Load Tests - 01 January 1975

STP33717S: Motion of Dislocation in Stainless Steel During the Fast Neutron Irradiation - 01 January 1975

STP33678S: Reactor Vessel Material Surveillance Program - 01 January 1975

STP33673S: Influence of Defects in Body-Centered Cubic Iron on Simulated Low-Energy Displacement Cascades - 01 January 1975

STP33679S: Evaluation of Commercial Production A533-B Plates and Weld Deposits Tailored for Improved Radiation Embrittlement Resistance - 01 January 1975

STP32251S: Acoustic Monitoring Systems to Assure Integrity of Nuclear Plants - 01 January 1975

STP32245S: Development of Acoustic Emission Testing for the Inspection of Gas Distribution Pipelines - 01 January 1975

STP35512S: Analysis of Filament-Reinforced Spherical Pressure Vessels - 01 January 1974

STP551-EB: Zirconium in Nuclear Applications - 01 January 1974

STP32107S: Effect of Thermomechanical Processing and Heat Treatment on the Properties of Zr-3Nb-1Sn Strip and Tubing - 01 January 1974

STP32108S: Potential for Improvement of Mechanical Properties in Zircaloy Cold-Rolled Strip and Sheet - 01 January 1974

STP32109S: Effect of the Annealing Temperature on the Creep Strength of Cold-Worked Zircaloy -4 Cladding - 01 January 1974

STP32110S: Thermomechanical Control of Texture and Tensile Properties of Zircaloy-4 Plate - 01 January 1974

STP32100S: Development of a Closed-End Burst Test Procedure for Zircaloy Tubing - 01 January 1974

STP32111S: Creep Strength of Zircaloy Tubing at 400°C as Dependent on Metallurgical Structure and Texture - 01 January 1974

STP32112S: Pilger Tooling Design for Texture Control - 01 January 1974

STP32114S: Operable Deformation Systems and Mechanical Behavior of Textured Zircaloy Tubing - 01 January 1974

STP32116S: Directionality of the Grain Boundary Hydride in Zircaloy-2 - 01 January 1974

STP32117S: Use of Ion Bombardment to Study Irradiation Damage in Zirconium Alloys - 01 January 1974

STP32118S: Mechanisms of Irradiation Creep in Zirconium-Base Alloys - 01 January 1974

STP32119S: In—Reactor Creep of Zr—2.5Nb Tubes at 570 K - 01 January 1974

STP32120S: In—Reactor Stress Relaxation of Zirconium Alloys - 01 January 1974

STP32121S: High Deformation Creep Behavior of 0.6-in.-Diameter Zirconium Alloy Tubes Under Irradiation - 01 January 1974

STP32122S: Suppression of Void Formation in Zirconium - 01 January 1974

STP32123S: Deformation of Irradiated Zirconium-Niobium Alloys - 01 January 1974

STP32101S: Uniform Ultrasonic Inspection of Fuel Sheath Tubing - 01 January 1974

STP32124S: Variation of Zircaloy Fracture Toughness in Irradiation - 01 January 1974

STP32125S: Strength and Ductility of Neutron Irradiated and Textured Zircaloy-2 - 01 January 1974

STP32126S: Plastic Instability in Irradiated Zr-Sn and Zr-Nb Alloys - 01 January 1974

STP32127S: Assessment of Fracture Studies on Zircaloy-2 Pressure Tubes - 01 January 1974

STP32102S: Defect Sensitivity in “Lamb Wave” Testing of Thin-Walled Tubing - 01 January 1974

STP32128S: Irradiation Damage Recovery in Some Zirconium Alloys - 01 January 1974

STP32129S: Stress Corrosion Cracking of Zircaloys in Iodine Containing Environments - 01 January 1974

STP32130S: Microstructure of the Oxide Films Formed on Zirconium-Based Alloys - 01 January 1974

STP32131S: Corrosion and Hydriding Performance of Zircaloy Tubing After Extended Exposure in the Shippingport Pressurized Water Reactor - 01 January 1974

STP32133S: Characterization of Zircaloy Oxidation Films - 01 January 1974

STP32135S: Fracture of Zircaloy-2 in an Environment Containing Iodine - 01 January 1974

STP32136S: Study of Zirconium Alloy Corrosion Parameters in the Advanced Test Reactor - 01 January 1974

STP32137S: Effect of Surface Treatment on the Irradiation Enhancement of Corrosion of Zircaloy-2 in HBWR - 01 January 1974

STP32103S: Improved Metallography of Zirconium Alloys - 01 January 1974

STP32099S: Zirconium for Nuclear Primary Steam Systems - 01 January 1974

STP32104S: Determination of Solid Solubility Limit of Hydrogen in Alpha Zirconium by Internal Friction Measurements - 01 January 1974

STP32105S: Dual Analysis of Longitudinal and Transverse Zirconium Tensile Stress-Strain Data - 01 January 1974

STP32106S: Determination of Complete Plane-Stress Yield Loci of Zircaloy Tubing - 01 January 1974

STP33144S: Fracture Mechanics Evaluation of the Integrity of an Inlet Nozzle of a Pressurized Water Reactor Vessel Following a Postulated Loss of Coolant - 01 January 1974

STP32216S: Erosion-Corrosion of Finned Heat Exchanger Tubes - 01 January 1974

STP38832S: Fatigue of Protective Metal Oxides in Combustion Chamber Exhaust Gases - 01 January 1973

STP38853S: Low-Cycle Fatigue Behavior of Types 304 and 316 Stainless Steel at LMFBR Operating Temperature - 01 January 1973

STP38864S: Low-Cycle Fatigue Behavior of Zircaloy at 573 K - 01 January 1973

STP38881S: Elevated Temperature Test of Welded Furnace Wall Sections - 01 January 1973

STP36497S: High-Strength Filaments for Cables and Lines - 01 January 1973

STP35439S: Effects of Microstructure on Swelling and Tensile Properties of Neutron-Irradiated Types 316 and 405 Stainless Steels - 01 January 1973

STP529-EB: Effects of Radiation on Substructure and Mechanical Properties of Metals and Alloys - 01 January 1973

STP35441S: Effects of Second-Phase Particles on Irradiation Swelling of Austenitic Alloys - 01 January 1973

STP35442S: Void Formation in Type 1.4988 Stabilized Stainless Steel - 01 January 1973

STP35443S: Swelling and Tensile Property Evaluations of High-Fluence EBR-II Thimbles - 01 January 1973

STP35444S: Neutron Irradiation Damage in a Precipitation-Hardened Aluminum Alloy - 01 January 1973

STP35431S: Radiation-Induced Changes in the Fracture Extension Resistance (R-Curve) of Structural Steels - 01 January 1973

STP35446S: A Comparison of the High-Temperature Damage Structures in Accelerator and Reactor Irradiated Molybdenum - 01 January 1973

STP35447S: On the Swelling Mechanism in the Irradiated Boron-Containing Stainless Steel - 01 January 1973

STP35448S: Nickel Ion Bombardment of Types 304 and 316 Stainless Steels: Comparison with Fast-Reactor Swelling Data - 01 January 1973

STP35449S: Void Swelling Behavior of Types 304 and 316 Stainless Steel Irradiated with 4-MeV Ni+ Ions - 01 January 1973

STP35451S: Studies of Void Formation in Proton-Irradiated Type 316 and Titanium-Modified 316 Stainless Steels - 01 January 1973

STP35452S: Ordered Defect Structures in Irradiated Metals - 01 January 1973

STP35454S: A Diffusion Model for the Effect of Applied Stress on Void and Loop Growth - 01 January 1973

STP35455S: Attrition and Stabilization of Void Nuclei: Critical Nucleus Size - 01 January 1973

STP35456S: Production of Voids in Stainless Steel by High-Voltage Electrons - 01 January 1973

STP35432S: Effect of Composition on the Sensitivity of Structural Steel to Irradiation Embrittlement - 01 January 1973

STP35458S: Void Formation in Some Nickel-Aluminum Alloys During 20-MeV C++ and 46.5 MeV Ni6+ Irradiation - 01 January 1973

STP35459S: Materials Performance Prediction from Irradiation Test Data - 01 January 1973

STP35460S: High-Temperature Embrittlement of Ferritic and Austenitic Stainless Steels Irradiated up to 1.6 × 1022 n/cm2 (> 0.1 MeV) - 01 January 1973

STP35461S: Effect of Irradiation on the Microstructure and Creep-Rupture Properties of Type 316 Stainless Steel - 01 January 1973

STP35463S: Ductility of Irradiated Type 316 Stainless Steel - 01 January 1973

STP35464S: Effects of Fast-Neutron Irradiation on Tensile Properties and Swelling Behavior of Vanadium Alloys - 01 January 1973

STP35465S: Burst Testing of Zircaloy Cladding from Irradiated Pickering-Type Fuel Bundles - 01 January 1973

STP35466S: Influence of Neutron Spectrum and Microstructure on the Postirradiation Creep-Rupture Behavior of an Austenitic Cr-Ni-Ti-B Steel - 01 January 1973

STP35467S: Fatigue Behavior of Irradiated Thin-Section Type 348 Stainless Steel at 550 F (288 C) - 01 January 1973

STP35468S: In-pile Stress Rupture Strength of Three Stabilized Austenitic Stainless Steels - 01 January 1973

STP35434S: On the Radiation Hardening Mechanism in Fe-C-Mn Type Alloys - 01 January 1973

STP35469S: Influence of Irradiation on the Creep/Fatigue Behavior of Several Austenitic Stainless Steels and Incoloy 800 at 700 C - 01 January 1973

STP35471S: Effect of Neutron Irradiation on Fatigue Crack Propagation in Types 304 and 316 Stainless Steels at High Temperatures - 01 January 1973

STP35472S: Effects of Irradiation on the Tensile and Structural Properties of FV548 Stainless Steel - 01 January 1973

STP35473S: Effect of Neutron Irradiation on Vanadium - 01 January 1973

STP35430S: Irradiation Strengthening and Fracture Embrittlement of A533-B Pressure Vessel Steel Plate and Submerged-Arc Weld - 01 January 1973

STP35435S: The Role of Some Alloying Elements on Radiation Hardening in Pressure Vessel Steels - 01 January 1973

STP35437S: Property Changes Resulting from Impurity-Defect Interactions in Iron and Pressure Vessel Steel Alloys - 01 January 1973

STP35438S: Damage-Function Analysis of Neutron-Induced Embrittlement in A302-B Steel at 550 F (288 C) - 01 January 1973

STP36516S: Centrifugal Liquid-Liquid Separation as Applied to Alkali Metal Reduction in Liquid Fuels by Aqueous Extraction - 01 January 1973

STP531-EB: Manual on Requirements, Handling, and Quality Control of Gas Turbine Fuel - 01 January 1973

STP36517S: Purification of Fuel Oils by Centrifugal Force - 01 January 1973

STP36518S: Survey of Trace Metals in Distillate Fuels - 01 January 1973

STP36520S: Analysis of Fuel Oils for Trace Metals - 01 January 1973

STP36511S: Effect of a Heavy Distillate Fuel on U-700 - 01 January 1973

STP36512S: Management of the Gas Turbine Fuel Systems - 01 January 1973

STP36510S: Operation of Gas Turbines on ASTM 3-GT Fuel - 01 January 1973

STP36513S: Experience with Distillate Fuels in Gas Turbines - 01 January 1973

STP36514S: Clean, Bright, and Dry - 01 January 1973

STP36515S: Electrical Purification of Gas Turbine Fuels - 01 January 1973

STP37902S: Corrosion Standards and Control in the Nuclear Power Industry - 01 January 1973

STP37899S: Corrosion Standards and Control in the Pipeline Industry - 01 January 1973

STP41382S: Pre-Service Cleaning Philosophy for Boiling Water Reactors - 01 January 1973

STP41385S: Cleaning of Fluid Systems and Associated Components During Construction Phase of Nuclear Power Plants - 01 January 1973

STP41388S: Cleaning Heat Exchanger Tubing in Industry with the M.A.N. Automatic On-Load Tube Brushing System - 01 January 1973

STP41389S: Experiences with Cleaning Stainless Steel Condensers on Allegheny Power System Stations - 01 January 1973

STP41390S: Premature Failure of Type 316 Stainless Steel Condenser Tubing in Brackish Water - 01 January 1973

STP41391S: Improving Condenser Performance with Continuous In-Service Cleaning of Tubes - 01 January 1973

STP38788S: Alloy Effects in Temper Embrittlement - 01 January 1972

STP499-EB: Temper Embrittlement of Alloy Steels - 01 January 1972

STP38784S: Temper Embrittlement Study of Ni-Cr-Mo-V Rotor Steels: Part II—Statistical Design and Analysis - 01 January 1972

STP38783S: Temper Embrittlement Study of Ni-Cr-Mo-V Rotor Steels: Part I—Effects of Residual Elements - 01 January 1972

STP38785S: Chemical Analytical Results—How Accurate? - 01 January 1972

STP38786S: Temper Embrittlement of Low Alloy Steels - 01 January 1972

STP38787S: Effect of Solute Elements on Temper Embrittlement of Low Alloy Steels - 01 January 1972

STP35392S: Detecting Acoustic Emission in Large Liquid Metal Cooled Fast Breeder Reactors - 01 January 1972

STP35393S: Acoustic Emission Testing of Pressure Vessels for Petroleum Refineries and Chemical Plants - 01 January 1972

STP34124S: Fatigue Crack Growth Analysis of Pressurized Water Reactor Vessels - 01 January 1972

STP38824S: Relationship Between Charpy V and Fracture Mechanics KIc Assessments of A533-B Class 2 Pressure Vessel Steel - 01 January 1972

STP34682S: Verification of Structural Integrity of Pressure Vessels by Acoustic Emission and Periodic Proof Testing - 01 January 1972

STP32063S: Investigation of Transition Temperature Tests for Line Pipe Materials - 01 January 1970

STP26865S: Comparison of Erosion Resistance of Standard Steam Turbine Blade and Shield Materials on Four Test Rigs - 01 January 1970

STP32074S: Metallography of Radioactive Materials at Oak Ridge National Laboratory - 01 January 1970

STP28627S: Chapter 3—Army Reactor Vessel Surveillance and Vessel Examination - 01 January 1970

STP481-EB: Analysis of Reactor Vessel Radiation Effects Surveillance Programs - 01 January 1970

STP28628S: Chapter 4—Commercial Reactor Vessel Surveillance - 01 January 1970

STP28625S: Chapter 1—Basis for Vessel Surveillance - 01 January 1970

STP28629S: Chapter 5—Neutron Dosimetry and Spectrum - 01 January 1970

STP28630S: Chapter 6—Surveillance Programs Critique and Recommendations - 01 January 1970

STP28626S: Chapter 2—Neutron Embrittlement of Pressure Vessel Steels—A Brief Review - 01 January 1970

STP484-EB: Irradiation Effects on Structural Alloys for Nuclear Reactor Applications - 01 January 1970

STP26615S: Neutron Irradiation Effects on Iron Containing Aluminum and Nitrogen - 01 January 1970

STP26617S: The Effect of Fast Neutron Irradiation on the Mechanical Properties of Some Quenched and Tempered Steels - 01 January 1970

STP26619S: Structure and Composition Effects on Irradiation Sensitivity of Pressure Vessel Steels - 01 January 1970

STP26620S: Effects of Irradiation in a Thermal Reactor on the Tensile Properties of Zircaloy 2 and 4 and Borated Stainless Steel - 01 January 1970

STP26622S: Influence of Irradiation Temperature on the Tensile Properties of Stainless Steel - 01 January 1970

STP26607S: Radiation Effects on the Metallurgical Fracture Parameters and Fracture Toughness of Pressure Vessel Steels - 01 January 1970

STP26623S: The Effect of Neutron Irradiation on the Mechanical Properties of Zirconium Alloy Fuel Cladding in Uniaxial and Biaxial Tests - 01 January 1970

STP26625S: Metallurgical Properties of Cold-Worked Zircaloy 2 Pressure Tubes Irradiated Under CANDU-PHW Power Reactor Conditions - 01 January 1970

STP26627S: The Temperature and Neutron Dose Dependence of Irradiation Growth in Zircaloy 2 - 01 January 1970

STP26629S: Quantitative Transmission Electron Microscopy of Bubbles in A1 and A1-A12O3 Alloys - 01 January 1970

STP26631S: The Mechanism and Kinetics of Void Growth During Neutron Irradiation - 01 January 1970

STP26633S: Void Formation in Proton Irradiated Stainless Steel - 01 January 1970

STP26635S: Considerations of Metal Swelling and Related Phenomena Caused by Fast Neutron Irradiation - 01 January 1970

STP26637S: Some Observations on the Structure and Tensile Properties of AISI Type 316 Steel as a Function of Fast Reactor Irradiation Temperature - 01 January 1970

STP26638S: Neutron Dosimetry for Fast Reactor Applications - 01 January 1970

STP26605S: Neutron Dosimetry for Reactor Pressure Vessel Applications - 01 January 1970

STP26640S: Neutron Fluence Limit Determinations for Some Fast Flux Test Facility Components - 01 January 1970

STP26641S: Axial Fatigue of Irradiated Stainless Steels Tested at Elevated Temperatures - 01 January 1970

STP26609S: The Effect of Hydrogen on the Ductile Properties of Irradiated Pressure Vessel Steels - 01 January 1970

STP26643S: Effect of Fast Neutron Irradiation on the Creep Rupture Properties of Type 304 Stainless Steel at 600 C - 01 January 1970

STP26645S: Uniaxial and Biaxial Creep Rupture of Type 316 Stainless Steel After Fast Reactor Irradiation - 01 January 1970

STP26646S: Effect of Irradiation on the Mechanical Properties of 19-9DL Alloy - 01 January 1970

STP26648S: Influence of Neutron Irradiation on the Creep Rupture Properties of a 16Cr-13Ni Steel - 01 January 1970

STP26649S: The Effects of Helium on the High-Temperature Ductility of Sandvik 12R72HV and Inco IN-744X - 01 January 1970

STP26651S: Correlation Between the Mechanical Properties and Microstructure of Irradiated Iron and Low-Carbon Steel - 01 January 1970

STP26652S: Irradiation Effects at Cryogenic Temperature on Tensile Properties of Titanium and Titanium-Base Alloys - 01 January 1970

STP26611S: Evaluation of the Embrittlement of Pressure Vessel Steels Irradiated in JPDR - 01 January 1970

STP26613S: Demonstration of Improved Radiation Embrittlement Resistance of A533B Steel Through Control of Selected Residual Elements - 01 January 1970

STP41845S: Initial Assessments of Notch Ductility Behavior of A533 Pressure Vessel Steel with Neutron Irradiation - 01 January 1969

STP457-EB: Irradiation Effects in Structural Alloys for Thermal and Fast Reactors - 01 January 1969

STP41846S: Notch Ductility, Tensile and Neutron Spectrum Analyses of PM-2A Reactor Pressure Vessel - 01 January 1969

STP41847S: Irradiation Effects in Pressure Vessel Materials for Steam-Cooled Fast Reactors - 01 January 1969

STP41841S: Comparison of In-Reactor Creep and Postirradiation Creep Tests of Structural Materials for Nuclear Applications - 01 January 1969

STP41848S: The Effect of Substructure on the Biaxial Strength and Irradiation Stability of ASTM A 302 Grade B Steel - 01 January 1969

STP41849S: Effects of Interstitial Elements on Radiation Hardening in Mild Steels - 01 January 1969

STP41850S: Radiation Hardening and Embrittlement in a Reactor Pressure Vessel Steel - 01 January 1969

STP41851S: Development of Austenitic Stainless Steels with Improved Resistance to Elevated-Temperature Irradiation Embrittlement - 01 January 1969

STP41852S: Development of a Titanium-Modified Hastelloy N with Improved Resistance to Radiation Damage - 01 January 1969

STP41853S: Effects of Yttrium on the Structure and Post-Irradiation Tensile Properties of an Iron-Chromium-Aluminum Alloy - 01 January 1969

STP41854S: Development of Fuel Cladding for Fast Reactors - 01 January 1969

STP41855S: Effect of Irradiation on Mechanical Properties of Cobalt-Base Alloys - 01 January 1969

STP41856S: Neutron Dosimetry for Fast-Reactor Irradiation and Surveillance Testing - 01 January 1969

STP41857S: High-Temperature Embrittlement of AISI Type 316 Austenitic Stainless Steels after Irradiation - 01 January 1969

STP41858S: Postirradiation Tensile Behavior of 300 Series Stainless Steels - 01 January 1969

STP41842S: High-Temperature Tensile Properties of Unirradiated and Thermal Reactor Irradiated Nimonic PE16 - 01 January 1969

STP41859S: Multiaxial In-Reactor Stress-Rupture Strength of Stainless Steels and a Nickel Alloy - 01 January 1969

STP41840S: The Effect of Cold Work, Thermal Treatment, and Neutron Irradiation on the Fracture Toughness of Zircaloy-2 - 01 January 1969

STP41860S: Comparison of Radiation Damage Studies and Fuel Cladding Performance for lncoloy-800 - 01 January 1969

STP41861S: Effects of Neutron Irradiation on Creep-Rupture Properties of Type 316 Stainless Steel Tubes - 01 January 1969

STP41843S: Irradiation-Induced Embrittlement in Stainless Steel at Elevated Temperature - 01 January 1969

STP41844S: Irradiation Tests of Several Steels for Reactor Pressure Vessels - 01 January 1969

STP43824S: Fatigue-Crack Growth and Propagation in 2.5Nb Zirconium Alloy Pressure Tubing - 01 January 1969

STP43825S: Embrittlement of Zircaloy-2 Pressure Tubes - 01 January 1969

STP43826S: The Effect of Orientation of Hydride Precipitates on the Fracture Toughness of Cold-Rolled Zircaloy-2 and 2.5Nb Zirconium - 01 January 1969

STP43818S: In-Reactor Creep of Zirconium-Alloy Tubes and Its Correlation with Uniaxial Data - 01 January 1969

STP43828S: The Effect of Neutron Irradiation and Cold Work on the Strain-Aging Behavior of Zircaloy-2 - 01 January 1969

STP43817S: The Effect of Texture and Strain Aging on Creep of Zircaloy-2 - 01 January 1969

STP43829S: Creep of Zirconium from 50 to 850 C - 01 January 1969

STP43830S: The Significance of Irradiation-Induced Creep on Reactor Performance of a Zircaloy-2 Pressure Tube - 01 January 1969

STP43831S: The Effect of Texture on the Torsional Yielding of Zircaloy Tubing - 01 January 1969

STP43832S: Failure of Pressurized Zircaloy Tubes During Thermal Excursions in Steam and in Inert Atmospheres - 01 January 1969

STP43833S: Corrosion and Failure Characteristics of Zirconium Alloys in High-Pressure Steam in the Temperature Range 400 to 500 C - 01 January 1969

STP43834S: The Corrosion Behavior of 2.5Nb Zirconium Alloy - 01 January 1969

STP43835S: Effects of Nuclear Radiation on the Corrosion, Hydriding, and Oxide Properties of Six Zirconium Alloys - 01 January 1969

STP43837S: The Use of Hydrogen Getters for Prevention of Hydrogen Embrittlement in Zirconium-Alloy Fuel Cans - 01 January 1969

STP43819S: Texture Changes Produced During Zircaloy-4 Tubing Fabrication: From Forged Billet to Finished Tubing - 01 January 1969

STP43820S: Texture Development and Texture Gradients in Zircaloy Tubing - 01 January 1969

STP43822S: The Mechanical Properties of Zircaloy-2 Tubing Containing Circumferentially Aligned Hydride - 01 January 1969

STP33653S: Some Microstructural and Alloying Effects Upon Low-Cycle Fatigue Life of Pressure Vessel Steels - 01 January 1969

STP46478S: Temper Embrittlement of Rotor Steels - 01 January 1968

STP46482S: Analysis of Rotor Steels for Residual Elements - 01 January 1968

STP46476S: Statistical Study of Factors Influencing Impact Strength of Turbine Generator Rotors—Influence of Temper Embrittlement - 01 January 1968

STP437-EB: Turbine Lubrication Problems - 01 January 1968

STP45876S: Turbine System Bearing Failures Generally Classified as the Machining Type - 01 January 1968

STP45875S: An Investigation of Wire-Wool Type Turbine Thrust Bearing Failures - 01 January 1968

STP45877S: Fire Resistant Fluids for Steam Turbine Electrohydraulic Control Applications - 01 January 1968

STP45878S: Vapor Space Corrosion Inhibition of Steam Turbine Lubricating and Cleaning Oils - 01 January 1968

STP45879S: Clean Oil Systems for Heavy Duty Gas Turbines - 01 January 1968

STP45883S: Nondestructive Testing of Graphite at the Los Alamos Scientific Laboratory - 01 January 1968

STP439-EB: Nondestructive Testing of Nuclear Graphite - 01 January 1968

STP45884S: Application of Alcohol Penetrant for Evaluation of Surface Porosity of Graphite Inserts for Rocket Nozzles - 01 January 1968

STP45885S: Prediction of Strength of Graphitic Material by Nondestructive Test Techniques - 01 January 1968

STP45882S: Infrared Testing of Bonds Between Graphite and Protective Coatings - 01 January 1968

STP45886S: Contact Microradiography of Graphite - 01 January 1968

STP45887S: A Novel Infrared Nondestructive Testing Technique For Determining the Thermal Conductivity of Graphite - 01 January 1968

STP45888S: Strength Predictions for Graphite: A Review of Prior Work at AVCO SSD - 01 January 1968

STP45889S: Low Voltage Radiographic and Micoradiographic Techniques for Graphite - 01 January 1968

STP46048S: Erosion of Steam Turbine Blade Shield Materials - 01 January 1967

STP48438S: Residual Elements and Their Effect on Applications of Austenitic Stainless Steels in the Power Industry - 01 January 1967

STP43798S: Measurement of Corona Discharge Behavior at Low Pressure and Vacuum - 01 January 1967

STP420-EB: Measurement of Dielectric Properties Under Space Conditions - 01 January 1967

STP43799S: Electrical Testing of Electrical Apparatus at High Temperatures in Vacuum - 01 January 1967

STP43797S: Problems with Dielectric Measurements at Cryogenic Temperatures - 01 January 1967

STP43800S: Measurement of Dielectric Properties of Materials Under Vacuum, Reactor Radiation, and Cryogenic Conditions - 01 January 1967

STP43801S: Parameters Affecting Dielectric Materials for Space Applications - 01 January 1967

STP43802S: In Situ Dielectric Property Measurements in Simulated Space Environments - 01 January 1967

STP41320S: Irradiation Damage in Mild Steel: A Comparison of Crack Arrest Test and Charpy Criteria and Influence of Neutron Spectrum - 01 January 1967

STP426-EB: Effects of Radiation on Structural Metals - 01 January 1967

STP41321S: Gas Release and Compression Properties in Beryllium Irradiated at 600 and 750 C - 01 January 1967

STP41322S: Creep of Annealed Type 304 Stainless Steel During Irradiation and Its Engineering Significance - 01 January 1967

STP41323S: An Electron Microscope Investigation of High-Temperature Embrittlement of Irradiated Stainless Steels - 01 January 1967

STP41324S: Review of Swedish Work on Irradiation Effects in Canning and Core Support Materials - 01 January 1967

STP41316S: Effects of Heat-Treatment and Irradiation on the High Temperature Tensile Properties of Austenitic Stainless Steels - 01 January 1967

STP41325S: Review of Swedish Work on Irradiation Effects in Pressure Vessel Steels and on Significance of Data Obtained - 01 January 1967

STP41326S: An Evaluation of Radiation Damage to Reactor Vessel Steels Using Both Transition Temperature and Fracture Mechanics Approaches - 01 January 1967

STP41327S: Nature of Radiation Damage to Engineering Properties of Various Stainless Steel Alloys - 01 January 1967

STP41328S: Applications of Fracture Mechanics in Evaluating Initiation and Propagation of Brittle Fracture in Reactor Structural Components - 01 January 1967

STP41329S: Neutron Irradiation Embrittlement of Several Higher Strength Steels - 01 January 1967

STP41330S: Implications of Embrittlement During the Life of a Zirconium Pressure Tube Reactor - 01 January 1967

STP41331S: Properties of Irradiated Materials Needed for the Design of Reactor Vessels. Part I, Water Cooled Reactors - 01 January 1967

STP41315S: Effect of Nitrogen on the Mechanical Properties of Neutron-Irradiated Pure Iron - 01 January 1967

STP41332S: Fatigue Properties of Irradiated Pressure Vessel Steels - 01 January 1967

STP41333S: Solutions to the Problems of High-Temperature Irradiation Embrittlement - 01 January 1967

STP41334S: Improved Postirradiation Tensile and Stress-Rupture Properties of Hastelloy X-280 - 01 January 1967

STP41335S: Effect of Neutron Irradiation on Mechanical Properties of AISI Type 347 Stainless Steel - 01 January 1967

STP41317S: Engineering Significance of Ferrite Grain Size on the Radiation Sensitivity of Pressure Vessel Steels - 01 January 1967

STP41336S: Effects of Neutron Irradiation on Creep-Rupture Properties of W-25RE Alloy - 01 January 1967

STP41337S: Metallurgical Variables as Possible Factors Controlling Irradiation Response of Structural Steels - 01 January 1967

STP41338S: Dose Rate, Annealing, and Stress Relaxation Studies of Radiation Hardening in Iron - 01 January 1967

STP41339S: Damaging Neutron Exposure Criteria for Evaluating the Embrittlement of Reactor Pressure Vessel Steels in Different Neutron Spectra - 01 January 1967

STP41340S: Cryogenic Radiation Effects on NERVA Structural Materials - 01 January 1967

STP41341S: Plastic Stability of Zr-2 Fuel Cladding - 01 January 1967

STP41342S: Influence of Boron on the Creep Rupture Properties of a Neutron Irradiated Precipitation Hardening Iron Base Alloy - 01 January 1967

STP41318S: Effects of Neutron Irradiation on the Elevated Temperature Mechanical Properties of Nickel-Base and Refractory Metal Alloys - 01 January 1967

STP41343S: Role of Pressure Vessel Surveillance Programs in Power Reactors: Summary and Analysis of Asme Panel Discussion - 01 January 1967

STP41319S: Irradiation Effects on the Mechanical Properties of Vanadium-Base Alloys - 01 January 1967

STP46031S: Effect of Metallurgical Variables on the Superconducting Properties of Metals and Alloys - 01 January 1966

STP387-EB: Behavior of Materials at Cryogenic Temperatures - 01 January 1966

STP46032S: Thermophysical Properties of Metals at Cryogenic Temperatures - 01 January 1966

STP46027S: Introduction - 01 January 1966

STP46029S: Some Basic and Engineering Considerations Regarding the Fracture of Metals at Cryogenic Temperatures - 01 January 1966

STP46028S: Plastic Behavior of Metals at Cryogenic Temperatures - 01 January 1966

STP46030S: Low-Temperature Phase Transformations - 01 January 1966

STP44637S: The Radiation-Induced Decomposition of Some Inorganic Sulfates - 01 January 1966

STP400-EB: Effects of High-Energy Radiation on Inorganic Substances - 01 January 1966

STP44638S: Activation and Sintering Behavior of Calcium Oxide—the Effect of Copper X-Irradiation on the Surface Area of the Oxide Produced by Thermal Decomposition - 01 January 1966

STP44639S: On the Dichroism in R-Bands Induced in γ-Irradiated Potassium Chloride Crystals - 01 January 1966

STP44633S: The Radiolytic Decomposition of Crystalline Alkali Metal and Alkaline Earth Bromates - 01 January 1966

STP44632S: The Thermal Decomposition of Irradiated Mercuric Oxalate - 01 January 1966

STP44634S: Thermal Decomposition of Gamma-Irradiated Barium Azide - 01 January 1966

STP44635S: Low-Temperature Annealing Processes in Alkali Halides - 01 January 1966

STP44636S: Electron Spin Resonance Spectra of Radiation — Damaged Inorganic Crystals - 01 January 1966

STP43737S: The Effects of Neutron Exposure and Reactor Environments on Stainless Steels - 01 January 1965

STP43738S: Evaluation and Application of Stainless Steels in Cryogenic Environments - 01 January 1965

STP43739S: Experience with Stainless Steels in Utility Power Plants - 01 January 1965

STP43524S: Effects of Irradiation in Iron and Steels - 01 January 1965

STP380-EB: Flow and Fracture of Metals and Alloys in Nuclear Environments - 01 January 1965

STP43525S: Low-Temperature Embrittlement of Iron, Iron Alloys, and Steels by Neutron Irradiations - 01 January 1965

STP43526S: Effect of Irradiation on Bend Transition Temperatures of Molybdenum- and Columbium-Base Alloys - 01 January 1965

STP43527S: Irradiation Effects on High-Temperature Reactor Structural Metals - 01 January 1965

STP43528S: Recovery of Defects in Neutron-Irradiated Tungsten - 01 January 1965

STP43529S: The Nature and Annealing Behavior of Irradiation Damage in Molybdenum - 01 January 1965

STP43530S: Effects of Irradiation in Austenitic Steels and Other High-Temperature Alloys - 01 January 1965

STP43531S: The Flow and Fracture Properties of Unirradiated Stainless Steels - 01 January 1965

STP43532S: The Combined Effects of Temperature and Irradiation on the Mechanical Properties of Austenitic Stainless Steels - 01 January 1965

STP43533S: The Effect of Irradiation Temperature on the Post-Irradiation Stress-Strain Behavior of Stainless Steel - 01 January 1965

STP43534S: In-Reactor Stress-Rupture Properties of a 20Cr-25Ni, Columbium-Stabilized Steel - 01 January 1965

STP43535S: New Information on Neutron Embrittlement and Embrittlement Relief of Reactor Pressure Vessel Steels - 01 January 1965

STP43536S: In-Depth Embrittlement of a Simulated Pressure Vessel Wall Of A302-B Steel - 01 January 1965

STP43537S: Strain-Cycle Phenomena In Thin-Wall Tubing - 01 January 1965

STP43538S: Effects of Irradiation on A302-B Steel Subjected to a Multiaxial Stress Distribution - 01 January 1965

STP43539S: In-Reactor Studies of Low-Cycle Fatigue Properties of a Nuclear Pressure Vessel Steel - 01 January 1965

STP43540S: Effects of Neutron Irradiation on the Flow and Fracture Behavior of Zircaloy-2 - 01 January 1965

STP43541S: In-Reactor Creep of Cold-Worked Zircaloy-2 - 01 January 1965

STP43542S: Gas Formation and Compression Fractures in Irradiated Beryllium - 01 January 1965

STP43520S: Mechanisms of Radiation Damage in Reactor Materials - 01 January 1965

STP43521S: Mechanisms of Radiation-Induced Mechanical Property Changes - 01 January 1965

STP43543S: The Use of Materials Properties by the Reactor Vessel Designer - 01 January 1965

STP43544S: The Significance of Recent Developments in Fracture Mechanics In Great Britain In Relation To The Safety Of Reactor Pressure Vessels - 01 January 1965

STP43545S: The Important Materials Parameters Affecting the Performance of Nuclear Reactor Pressure Vessels - 01 January 1965

STP43546S: Crack Propagation Tests on Zircaloy-2 Reactor Pressure Tubing in Both the Normal and Hydrided Conditions - 01 January 1965

STP43547S: Insurance Aspects of Radiation Damage in Reactor Structures - 01 January 1965

STP43522S: Irradiation Hardening and Embrittlement in Body-Centered Cubic Transition Metals - 01 January 1965

STP43523S: Computer Studies of Neutron Irradiation and Annealing in Finite BCC Iron Specimens - 01 January 1965

STP44608S: Proton and Electron Permanent Damage in Silicon Semiconductor Devices - 01 January 1965

STP384-EB: Radiation Effects in Electronics - 01 January 1965

STP44609S: The Effects of Ionizing Radiation on Transistor Gain - 01 January 1965

STP44610S: Radiation Induced Surface Effects on Selected Semiconductor Devices - 01 January 1965

STP44611S: Influence of Operating Conditions on Radiation Damage to Transistor Gain - 01 January 1965

STP44612S: Transient Radiation Effects on Traveling-Wave Tubes - 01 January 1965

STP44604S: Transient High Energy Effects in Semiconductors and Insulators - 01 January 1965

STP44613S: Development of a Radiation Tolerant All Solid State Tracking and Command System - 01 January 1965

STP44614S: A Computor Assessment of Fast Neutron Flux - 01 January 1965

STP44615S: Remarks on Correlation Studies - 01 January 1965

STP44605S: EPR Measurements of Radiation Immunization in Poly (methyl Methacrylate) by Organic Additives - 01 January 1965

STP44603S: Radiation-Induced Electronic Phenomena in Polyethylene - 01 January 1965

STP44606S: Neutron and Neutron Spectra Contribution to Damage in Silicon F.E.T.'s - 01 January 1965

STP44607S: Transient Radiation Effects in Semiconductor Devices - 01 January 1965

STP56S-EB: 1964 Supplement to the Bibliography and Abstracts on Electrical Contacts, Circuit Breakers, and ARC Phenomena - 01 January 1965

STP47055S: Specific Solar Flare Events and Associated Radiation Doses - 01 January 1964

STP47058S: Vacuum Systems for Dynamic Studies of the Engineering Properties of Materials During Exposure to Nuclear Reactor Irradiation - 01 January 1964

STP346-EB: Symposium on Electrical Insulating Gases - 01 January 1964

STP44525S: The Use of Sulfur Hexafluoride as a Gaseous Dielectric - 01 January 1964

STP44526S: Electrical Insulating Gases: Hexafluoroethane and Octafluorocyclobutane - 01 January 1964

STP44524S: Gaseous Insulation: Its Importance and Need for Test Methods - 01 January 1964

STP44527S: Fluorocarbon Gases and Volatile Liquids: Properties and Applications - 01 January 1964

STP44528S: Round-Robin Tests on Test Cells for Insulating Gases - 01 January 1964

STP359-EB: Symposium on the Chemical and Physical Effects of High-Energy Radiation on Inorganic Substances - 01 January 1964

STP45818S: Paramagnetic Resonance of Transition Elements and Irradiated Substances - 01 January 1964

STP45819S: Thermal Decomposition of Irradiated Nickel Oxalate - 01 January 1964

STP45817S: Use of Color Centers for Detection and Measurement of Defects - 01 January 1964

STP45820S: X-Ray Diffraction Studies of Silver Permanganate - 01 January 1964

STP45821S: Radiation-Induced Changes in Reactivity of Ammonium Perchlorate - 01 January 1964

STP45822S: Radiation-Induced Decomposition of Inorganic Solids - 01 January 1964

STP45823S: Low-Energy Radiation Damage Processes in a Body-Centered Cubic Lattice - 01 January 1964

STP45824S: Effect of Ionizing Radiation on Alkali Halides - 01 January 1964

STP47075S: Neutron Irradiation and Cold Work Effects on Zircaloy-2 Corrosion and Hydrogen Pickup - 01 January 1964

STP47076S: Factors Limiting the Use of Zirconium Alloys in Superheated Steam - 01 January 1964

STP47070S: The Development of the Zircaloys - 01 January 1964

STP47072S: Zircaloy-2 Corrosion In-Pile in Aqueous Homogeneous Reactor Solutions - 01 January 1964

STP47074S: Effect of Hydride Morphology on the Tensile Properties of Zircaloy-2 - 01 January 1964

STP56R-EB: 1963 Supplement to the Bibliography and Abstracts on Electrical Contacts, Circuit Breakers, and ARC Phenomena - 01 January 1964

STP44437S: A Laboratory Scale Filament Winding System to Produce Pressure Vessels Rapidly and Simply - 01 January 1963

STP44438S: Photoelastic Studies of Filament-Wound Pressure Vessels - 01 January 1963

STP46409S: Continuous Automatic Boiler Water Silica Analysis - 01 January 1963

STP41746S: Significance of Neutron Spectrum on Radiation Effects Studies - 01 January 1963

STP341-EB: Symposium on Radiation Effects on Metals and Neutron Dosimetry - 01 January 1963

STP41747S: Fast-Neutron Dosimetry at the MTR-ETR Site - 01 January 1963

STP41748S: Fast Neutron Dosimetry for Long-Term Irradiations - 01 January 1963

STP41749S: The Use of Semiconductor Lithium Drifted P-I-N Junction Detectors for Dosimetry - 01 January 1963

STP41750S: Brittle Fracture and Irradiation Effects in Ferritic Pressure Vessel Steels - 01 January 1963

STP41751S: Effects of Radiation on Two Low-Alloy Steels at Elevated Temperatures - 01 January 1963

STP41752S: Effect of Neutron Irradiation at 550 F on Charpy Impact Properties of ASTM A 302 Grade B Steel - 01 January 1963

STP41753S: Surveillance Tests on Structural Materials in Nuclear Reactors - 01 January 1963

STP41754S: Irradiation Embrittlement and Hardening of Steels and Zircaloy-2 in Pressurized Components - 01 January 1963

STP41755S: Effects of Neutron Spectrum and Dose Rate on Radiation Hardening and Embrittlement in Steels - 01 January 1963

STP41756S: A Study of Neutron Irradiation in Alpha Iron and A 1Cr-0.5Mo Pressure Vessel Steel - 01 January 1963

STP41757S: Swedish Studies on Irradiation Effects in Structural Materials - 01 January 1963

STP41758S: Radiation Effects in Reactor Structural Materials - 01 January 1963

STP41759S: Radiation-Induced Property Changes in AISI Type 347 Stainless Steel - 01 January 1963

STP41742S: Structure of Displacement Cascades Produced by Neutron Irradiation - 01 January 1963

STP41760S: Effect of Neutron Bombardment on Stress-Rupture Properties of Some Structural Alloys - 01 January 1963

STP41761S: In-Reactor Creep Measurements on Zircaloy-2 - 01 January 1963

STP41762S: Neutron Irradiation Effects in A-286, Hastelloy X, and René 41 Alloys - 01 January 1963

STP41741S: Mechanisms of Atomic Displacements Induced by Radiation - 01 January 1963

STP41743S: Mechanical Properties of Irradiated Iron and Iron Alloys - 01 January 1963

STP41744S: Effects of Neutron Irradiation on Precipitation-Hardening Alloys - 01 January 1963

STP41745S: Fundamental Aspects of Radiation Effects on Diffusion-Controlled Reactions in Alloys - 01 January 1963

STP56Q-EB: 1962 Supplement to the Bibliography and Abstracts on Electrical Contacts - 01 January 1963

STP44388S: In-Pile Fission-Gas Release from UO2 - 01 January 1962

STP306-EB: Symposium on Radiation Effects in Refractory Fuel Compounds - 01 January 1962

STP44389S: Continuous Release of Fission Gas from UO2 During Irradiation - 01 January 1962

STP44390S: Some Comments Regarding Sintering Characteristics in a Radiation Environment - 01 January 1962

STP44391S: Mechanism of Irradiation Damage in Uranium Monocarbide - 01 January 1962

STP44392S: Water-Vapor Corrosion of Beryllia - 01 January 1962

STP44393S: The Irradiation and Examination of a Plutonium-Uranium Oxide Fast Reactor Fuel - 01 January 1962

STP44383S: Voids in Irradiated UO2 - 01 January 1962

STP44384S: The Heat Rating Required to Produce Central Melting in Various UO2 Fuels - 01 January 1962

STP44382S: Some Consequences of Excess Oxygen in UO2 - 01 January 1962

STP44385S: Fission Fragment Tracks in Thin Films of UO2 - 01 January 1962

STP44386S: Effects of Burnup on Certain Ceramic Fuel Materials - 01 January 1962

STP44387S: Study of Factors Controlling the Release of Xenon-133 from Bulk UO2 - 01 January 1962

STP45078S: Cavitation in Hydraulic Turbines - 01 January 1962

STP41432S: Part I. Iron, Carbon Steel, and the Stainless Steels - 01 January 1962

STP314-EB: Reactor Structural Materials: Engineering Properties as Affected by Nuclear Reactor Service - 01 January 1962

STP41433S: Part II. Nickel and Cobalt Alloys - 01 January 1962

STP41434S: Part III. Aluminum and Titanium - 01 January 1962

STP41435S: Part IV. Zirconium Alloys - 01 January 1962

STP43696S: Determining the Functional Life of Turbine Oils - 01 January 1962

STP321-EB: Symposium on Turbine Oils (1962) - 01 January 1962

STP43690S: Problem Areas in Laboratory Testing of Turbine-Type Oils - 01 January 1962

STP43689S: The Role of Base Oils and Additives in Modern-Day Turbine Oils - 01 January 1962

STP43691S: Rust Inhibitors—Their Evaluation and Performance - 01 January 1962

STP43692S: Experience with Enhanced Load-Carrying Type Turbine Oils in the Royal Canadian Navy - 01 January 1962

STP43693S: Vapor Space Inhibited Steam Turbine Oils - 01 January 1962

STP43694S: The Changing Requirements for Turbine Oils - 01 January 1962

STP43695S: Fleet Experience with Navy Turbine Oils—Are Specification Methods Significant? - 01 January 1962

STP56P-EB: 1961 Supplement to the Bibliography and Abstracts on Electrical Contacts - 01 January 1962

STP56O-EB: 1960 Supplement to the Bibliography and Abstracts on Electrical Contacts - 01 January 1961

STP44240S: D 860 - 54 Standard Method of Sampling Water from Boilers - 01 January 1960

STP48528S: D 860 - 54 Standard Method of Sampling Water from Boilers - 01 January 1960

STP46960S: The Why and How of Cable Oil Tests A Review - 01 January 1960

STP253-EB: Symposium on High-Voltage Cable Insulation - 01 January 1960

STP46958S: Introduction - 01 January 1960

STP46961S: The Utility Viewpoint on Cable Oils - 01 January 1960

STP46959S: Paper for High-Voltage Cables - 01 January 1960

STP44337S: Instrumentation for Nucleonics - 01 January 1960

STP261-EB: Symposium on Radioisotopes in Metals Analysis and Testing - 01 January 1960

STP44338S: Metals Analysis by Radioactivation - 01 January 1960

STP44339S: Principles of Isotope Dilution Assays - 01 January 1960

STP44336S: Nucleonics in Analysis - 01 January 1960

STP44340S: Neutron Activation Analysis of Traces of Molybdenum in Tungsten - 01 January 1960

STP44341S: Application of the (n,α) Reaction - 01 January 1960

STP44342S: Experience with Neutron Activation in the Analysis of Aluminum - 01 January 1960

STP44343S: Training Industrial Personnel in Radioisotope Utilization - 01 January 1960

STP44344S: Summary of Panel Discussion - 01 January 1960

STP43665S: Electron Metallography of Neutron-Irradiated Steels - 01 January 1960

STP268-EB: Symposium on Applied Radiation and Radioisotope Test Methods - 01 January 1960

STP39369S: Grain Boundary Segregation Studies by Activation - 01 January 1960

STP46968S: Temperature Rise in Structures Due to Solar Heating - 01 January 1960

STP46333S: Test Methods Used for Zirconium and Zirconium Alloy in the Naval Reactor Program - 01 January 1960

STP46334S: Effects of Heat Treatments on the Tensile and Corrosion Properties of Zircaloy 2 - 01 January 1960

STP46340S: Coulometric Determination of Tin with Electrolytically Generated Iodine: Application to Analysis of Zircaloy - 01 January 1960

STP46350S: Solar Distillation of Saline Water with Particular Regard to Materials Problems - 01 January 1960

STP39592S: Irradiation of Some Pressure-Vessel Steels - 01 January 1960

STP276-EB: Materials in Nuclear Applications - 01 January 1960

STP39593S: Neutron Radiation Embrittlement at 500 and 650 F of Reactor Pressurf Vessel Steels - 01 January 1960

STP39594S: Dynamic Radiation Effects Testing Methods - 01 January 1960

STP39595S: Radiation Effects in Steel - 01 January 1960

STP39584S: Techniques for Measuring Reactor Neutron Spectra - 01 January 1960

STP39597S: The Significance to ASTM of Postirradiation Effects in Irradiated Materials - 01 January 1960

STP39598S: Electron Spin Resonance Studies of Free Radicals in Irradiated Materials - 01 January 1960

STP39599S: Postirradiation Oxidation and Molecular Weight Changes in Polystyrene and Poly(Methyl Methacrylate) - 01 January 1960

STP39600S: Postirradiation Dielectric Properties of Silicones - 01 January 1960

STP39601S: Postirradiation Effects: Monomers and Polymers - 01 January 1960

STP39605S: Some Refractory Uranium Compounds Preparation and Properties - 01 January 1960

STP39606S: Dry Pressing Ceramic Fuel Elements to Close Tolerances - 01 January 1960

STP39585S: Reactor Monitoring by Calorimetry - 01 January 1960

STP39607S: Fabrication and Evaluation of Urania-Alumina Fuel Elements and Boron Carbide Burnable Poison Elements - 01 January 1960

STP39608S: Silicon Carbide Clad Graphite Matrix Fuel Elements - 01 January 1960

STP39609S: Graphite as a Fuel Matrix - 01 January 1960

STP39610S: Fabrication of U3O8 - Aluminum Dispersion Fuel Elements by Extrusion - 01 January 1960

STP39582S: The Radiochemical Determination of Uranium Burnup - 01 January 1960

STP39586S: Removal Dose for Monitoring Effects of X-Rays and Gamma Rays - 01 January 1960

STP39587S: Dosimetry Nomenclature in the United States - 01 January 1960

STP39588S: Dosimetry in Europe and the USSR - 01 January 1960

STP39589S: Effects of Gamma Radiation on Some Electrical Properties of TFE-Fluorocarbon Plastics - 01 January 1960

STP39590S: Standardization of Terminology for Gamma and Electron Beam Radiation Sources - 01 January 1960

STP39591S: Atomistic Interpretation of Radiation Effects in Metals - 01 January 1960

STP39583S: Recent Developments in Gamma Ray Dosimetry - 01 January 1960

STP44350S: Simplified Metallographic Techniques for Nuclear Reactor Materials - 01 January 1960

STP46370S: Measurement of the Energy Absorbed from Pile Neutrons - 01 January 1960

STP286-EB: Symposium on Radiation Effects and Radiation Dosimetry - 01 January 1960

STP46371S: Neutron Dosimetry for Materials Irradiation Studies - 01 January 1960

STP46372S: Neutron Spectrum Determinations at Low Flux Levels - 01 January 1960

STP46373S: Radiation Damage in Steel: Considerations Involving the Effect of Neutron Spectra - 01 January 1960

STP46363S: Irradiation Testing of Enrico Fermi Prototype Fuel Pins in the CP-5 Reactor - 01 January 1960

STP46361S: Introduction - 01 January 1960

STP46364S: Effect of Neutron Irradiation on Charpy V and Drop-Weight Test Transition Temperatures of Various Steels and Weld Metals - 01 January 1960

STP46362S: Determinant Sample Parameters in Radiation Effects Testing of High Polymers - 01 January 1960

STP46365S: Reactor Spectra Considerations in Radiation Effects Predictions - 01 January 1960

STP46366S: Radiochemistry and Mass Spectrometry in Fuel Depletion Studies - 01 January 1960

STP46367S: Effect of Sample Parameters on Energy Absorption from a Neutron Beam - 01 January 1960

STP46368S: High-Intensity Gamma Ray Dosimetry - 01 January 1960

STP46369S: A Solid State Bragg-Gray Cavity Chamber - 01 January 1960

STP56N-EB: 1959 Supplement to the Bibliography and Abstracts on Electrical Contacts - 01 January 1960

STP44201S: Encyclopedia of Electrical Insulating Materials - 01 October 1959

STP39334S: Materials in the Nuclear Age - 01 January 1959

STP56M-EB: 1958 Supplement to the Bibliography and Abstracts on Electrical Contacts - 01 January 1959

STP45015S: Evaluation of Rubber Deterioration by Means of Phosphorus-32 - 01 January 1958

STP215-EB: Symposium on Radioisotopes - 01 January 1958

STP45016S: Autoradiography as a Testing Technique - 01 January 1958

STP45017S: Use of Radioactive Tracers in the Study of Soil Removal and Detergency - 01 January 1958

STP45018S: Refinery Scale Applications of Radioactive Tracers - 01 January 1958

STP45019S: Activation Analysis for Industry - 01 January 1958

STP45014S: Electroplating and Metal Preservation Studies Utilizing Radioisotopes - 01 January 1958

STP45020S: Thickness, Density and Concentration Gaging with Radioisotopes - 01 January 1958

STP45021S: Will ASTM Standards be Influenced by Radiation Effects in Metals? - 01 January 1958

STP45022S: The Problem of Establishing Specifications for Irradiated Organic Materials - 01 January 1958

STP48051S: The Beckman Dissolved Oxygen Analyzer - 01 January 1958

STP48052S: Evaluation of Hartmann and Braun Dissolved Oxygen Recorder for Boiler Feedwater - 01 January 1958

STP48053S: Determination of Dissolved Oxygen by Means of the Cambridge Analyzer - 01 January 1958

STP41984S: A Nondestructive Test for Intergranular Corrosion in Stainless Steel - 01 January 1958

STP223-EB: Symposium on Nondestructive Tests in the Field of Nuclear Energy - 01 January 1958

STP41985S: Two Applications of Eddy Current Instruments to Testing of Zircaloy Core Components - 01 January 1958

STP41986S: The Use of Penetrants for Inspection of Small Diameter Tubing - 01 January 1958

STP41978S: Introduction to Eddy Current Methods and Techniques - 01 January 1958

STP41987S: An Approach to Versatility in Eddy Current Testing - 01 January 1958

STP41988S: Radiography of Materials Used in the Nuclear Energy Field - 01 January 1958

STP41989S: Radiography with Thulium Sources - 01 January 1958

STP41990S: Measurement of Density of Uranium Metal by Radiation Absorption - 01 January 1958

STP41991S: Ultrasonic Testing as a Method of Determining Variables in Processing Zircaloy and Hafnium - 01 January 1958

STP41992S: Minimizing the Effect of Probe-to-Metal Spacing in Eddy Current Testing - 01 January 1958

STP41993S: Reduction of Probe-Spacing Effect in Pulsed Eddy Current Testing - 01 January 1958

STP41976S: Symposium on Nondestructive Tests in the Field of Nuclear Energy: Introduction - 01 January 1958

STP41994S: Eddy Current Measurement of Clad Thickness - 01 January 1958

STP41995S: Testing of Cylindrical Fuel Elements with the Cyclograph - 01 January 1958

STP41996S: Nickel Thickness Gage - 01 January 1958

STP41997S: A High Precision Density Times Thickness Gage - 01 January 1958

STP41998S: Ultrasonic Transmission Tester for Detection of Unbonded Areas - 01 January 1958

STP41999S: An Ultrasonic Scanner and Recording System - 01 January 1958

STP42001S: Applications of Lamb Waves in Ultrasonic Testing - 01 January 1958

STP42002S: Radiography of Fuel Elements and Fuel Materials Using Cesium-137 - 01 January 1958

STP42003S: Eddy Current Techniques for Testing Liquid Metal Bonding - 01 January 1958

STP42004S: Electrode Potential Method of Bond Testing - 01 January 1958

STP42005S: Nondestructive Bond Inspection Test by Electric Resistance Measurement for Complete Flat-Plate Fuel Element Subassemblies - 01 January 1958

STP42006S: Measurement of Cladding Thickness on Uranium by Autoradiography - 01 January 1958

STP41979S: Survey of Ultrasonic Methods and Techniques - 01 January 1958

STP42007S: Radiographic Inspection of Nuclear Core Materials and Components - 01 January 1958

STP42008S: Techniques for X-Ray Examinations of End-Weld Closures of Cylindrical Fuel Elements - 01 January 1958

STP42009S: Helium Leak Detection Techniques - 01 January 1958

STP42010S: Helium Leak Detector Test for Nuclear Reactor Welds - 01 January 1958

STP42011S: Nickel Depth Meter - 01 January 1958

STP42012S: Thermal Testing of Reactor Fuel Elements - 01 January 1958

STP42013S: A Recording X-Ray Photometer - 01 January 1958

STP42014S: Two Methods for Measuring Total Uranium Content in Co-Extruded AlU3O8 Reactor Fuel Plates - 01 January 1958

STP42015S: Approximate Determination of Enrichment of Reactor Fuel Element Plates with Improvised Gamma Ray Spectrometer - 01 January 1958

STP42016S: A Nondestructive Method for Fuel Assaying - 01 January 1958

STP42017S: A Technique for Gamma Radiographic Inspection of Parallel-Plate Fuel Assemblies - 01 January 1958

STP42018S: A Panoramic Camera for Inspecting Walls of Deep Narrow Slots - 01 January 1958

STP41977S: Nondestructive Testing in the Nuclear Energy Field - 01 January 1958

STP41980S: Survey of Radiation Techniques - 01 January 1958

STP41981S: Production Inspection of Pipe and Tubing by the Immersed Ultrasonic Method - 01 January 1958

STP41982S: An Eddy Current Test for Capillary Tubing - 01 January 1958

STP41983S: Inspection of Small Diameter Tubing by Eddy Current Methods - 01 January 1958

STP47749S: Rotor Forgings for Power Equipment Manufacturers - 01 January 1958

STP231-EB: Symposium on Brittle Failure of Rotor Forgings - 01 January 1958

STP47750S: The Work of the Task Group on Brittle Failure With Respect to Research - 01 January 1958

STP47751S: Requirements for Turbine and Generator Rotor Forgings - 01 January 1958

STP47747S: Introduction - 01 January 1958

STP47752S: Influence of Geometric Factors on Results of Ultrasonic Testing of Heavy Forgings - 01 January 1958

STP47753S: The Axial Test Bore in Turbo-Generator Rotors - 01 January 1958

STP47748S: Inspection of Large Rotor Forgings - 01 January 1958

STP39469S: Radioactive Waste Processing Control, Shippingport Atomic Power Station - 01 January 1958

STP56L-EB: 1957 Supplement to the Bibliography and Abstracts on Electrical Contacts - 01 January 1958

STP46275S: Variability of Dielectric Breakdown in Sheet Insulation - 01 January 1957

STP188-EB: Symposium on Minimum Property Values of Electrical Insulating Materials - 01 January 1957

STP46276S: The Establishment of Minimum Quality Levels of Sheet Insulation - 01 January 1957

STP46273S: Significance of Minimum Property Values of Electrical Insulating Materials - 01 January 1957

STP46277S: Low-Temperature Resistance Test Methods for Non-Rigid Insulation - 01 January 1957

STP46278S: Statistical Treatment of Heat-Aging Studies on Varnished Glass Cloth - 01 January 1957

STP46279S: Quality Level Cannot be Determined by “Go”-“No Go” Gage - 01 January 1957

STP46274S: Extremal Nature of Dielectric Breakdown—Effect of Sample Size - 01 January 1957

STP48035S: Steam Purity Determination by Tracer Techniques - 01 January 1957

STP192-EB: Symposium on Steam Quality - 01 January 1957

STP48033S: Introduction - 01 January 1957

STP48036S: Comments on Corrections to Steam Conductivity Measurements - 01 January 1957

STP48034S: Measurement and Purification of Steam to 0.01 ppm Total Dissolved Solids - 01 January 1957

STP46284S: Corona Resistance Test Method for Laminates, Molded, and Cast Materials - 01 January 1957

STP198-EB: Symposium on Corona - 01 January 1957

STP46281S: Introduction - 01 January 1957

STP46285S: Preliminary Investigation of Proposed Pulse Method for Measuring Ionization - 01 January 1957

STP46286S: Corona Detection and Measurement at Sixty Cycles - 01 January 1957

STP46287S: Test Methods for Measuring Energy in a Gas Discharge - 01 January 1957

STP46282S: Preliminary Corona Resistance Test Results from IEC Activities - 01 January 1957

STP46283S: Effects of Corona on Plastic Laminates - 01 January 1957

STP208-EB: Symposium on Radiation Effects on Materials-Volume 1 - 01 January 1957

STP44167S: Self-Limitation of Radiation Effects on Graphite - 01 January 1957

STP44168S: Survey of the Effects of Neutron Bombardment on Structural Materials - 01 January 1957

STP44169S: A Summary of the Effect of Radiation on Some Plastics and Elastomers - 01 January 1957

STP44170S: The Problem of Establishing Specifications for Irradiated Organic Materials - 01 January 1957

STP44171S: Effect of Irradiation on the Notched-Bar Impact Properties of Some Plain-Carbon Steels - 01 January 1957

STP44172S: Radiation Effects on Welds and Notches in Plain Carbon Steels, Stainless Steels, and Non-Ferrous Alloys - 01 January 1957

STP44173S: Fast Neutron Effects on Tensile and Hardness Properties of Type 347 Stainless Steel - 01 January 1957

STP44174S: Will ASTM Standards be Influenced by Radiation Effects in Metals? - 01 January 1957

STP44175S: Effects of Radiation Damage on Precipitation-Hardening Alloys, with Special Reference to Copper-Iron Alloys - 01 January 1957

STP44161S: A Radiation-Effects Program - 01 January 1957

STP44160S: Displaced Atoms in Solids—Comparison Between Theory and Experiment - 01 January 1957

STP44162S: The Mechanics of Testing Irradiated Materials - 01 January 1957

STP44163S: Problems of Dosimetry as Applied to Radiation Effects Studies - 01 January 1957

STP44164S: Westinghouse Testing Reactor - 01 January 1957

STP44165S: Survey of Radiation Effects on Fuel Materials - 01 January 1957

STP44166S: Influence of Heat Treatment on Irradiation-Induced Dimensional Changes in Some Uranium-Zirconium Alloys - 01 January 1957

STP211-EB: Symposium on Steam Turbine Oils - 01 January 1957

STP48039S: Organizational and Functional Aspects of Section on Oil Systems for Turbines, Technical Committee C, of ASTM Committee D-2 - 01 January 1957

STP48042S: Rusting in Turbine Oil Systems - 01 January 1957

STP48043S: Monomolecular Films of Rust-Preventive Additives - 01 January 1957

STP48040S: Laboratory Evaluation of Fire-Resistant Turbine Fluids - 01 January 1957

STP48044S: A Laboratory Device for the Water Leaching of Additives in Turbine Oils - 01 January 1957

STP48045S: Practices for Determining the Expected Life of Used Turbine Oils - 01 January 1957

STP48046S: Evaluation and Performance of Turbine Oils - 01 January 1957

STP48489S: Nondestructive Testing of Uranium - 01 January 1957

STP46298S: The Use of Solid and Liquid Catalysts for the Accelerated Aging Testing of Transformer Oil - 01 January 1957

STP218-EB: Symposium on Insulating Oils - 01 January 1957

STP46296S: Introduction - 01 January 1957

STP46297S: Evaluation of Laboratory Tests as Indicators of the Service Life of Uninhibited Electrical Insulating Oils - 01 January 1957

STP56K-EB: 1956 Supplement to the Bibliography and Abstracts on Electrical Contacts - 01 January 1957

STP48020S: Catalysts for Accelerated Aging Testing of Transformer Oil - 01 January 1956

STP172-EB: Evaluation of Insulating Oils—European Development - 01 January 1956

STP48021S: The Performance Characteristics of Used Insulating Oils - 01 January 1956

STP48022S: The Evaluation of Inhibited Transformer Oils - 01 January 1956

STP44095S: Influence of Water Composition on Corrosion in High-Temperature, High-Purity Water - 01 January 1956

STP179-EB: Symposium on High-Purity Water Corrosion - 01 January 1956

STP44096S: Effect of Material Composition in High-Temperature Water Corrosion - 01 January 1956

STP44097S: Special Corrosion Study of Carbon and Low-Alloy Steels - 01 January 1956

STP44094S: The Use of Water in Atomic Reactors - 01 January 1956

STP56J-EB: 1955 Supplement to the Bibliography and Abstracts on Electrical Contacts - 01 January 1956

STP56I-EB: 1954 Supplement to the Bibliography and Abstracts on Electrical Contacts - 01 January 1955

STP47984S: Design of Radioisotope Laboratories for Low and Intermediate Levels of Activity - 01 January 1954

STP159-EB: Symposium on Radioactivity—An Introduction - 01 January 1954

STP47981S: Foreword and Introduction - 01 January 1954

STP47985S: Training Personnel in Radioisotope Techniques - 01 January 1954

STP47986S: Nuclear Radiation—Its Detection and Measurement - 01 January 1954

STP47982S: Properties and Uses of Radioisotopes - 01 January 1954

STP47987S: Management Problems Resulting from Radioisotope Utilization by Industry - 01 January 1954

STP47983S: Applications of Radioactive Measurements to ASTM Work - 01 January 1954

STP46788S: A Method for Evaluation of the Thermal Aging Stability of Flexible Sheet Insulation - 01 January 1954

STP161-EB: Symposium on Temperature Stability of Electrical Insulating Materials - 01 January 1954

STP46789S: Effect of Elevated Temperature on Silicone Varnished Glass Fabric for Electrical Insulation - 01 January 1954

STP46780S: Dielectric Measurements on Plastics at High Temperatures - 01 January 1954

STP46778S: Introduction - 01 January 1954

STP46781S: Electrical Resistivity of Bonded Micaceous Materials at Elevated Temperatures - 01 January 1954

STP46779S: Measurement of Dielectric Properties at Temperatures up to 500 C - 01 January 1954

STP46782S: Test Methods for Studying Thermal Stability and Heat Aging of Electrical Insulating Varnishes - 01 January 1954

STP46783S: Thermal Stability of Insulating Fabrics - 01 January 1954

STP46784S: Electrical Properties of Thermosetting Plastics at Elevated Temperatures - 01 January 1954

STP46785S: Thermal Stability of Polyvinyl Chloride Insulating Compounds - 01 January 1954

STP46786S: The Deflected Beam—Film Rupture Test Applied to Sheet Insulation - 01 January 1954

STP46787S: Heat Aging Characteristics of Insulating Varnishes - 01 January 1954

STP56H-EB: 1952 and 1953 Supplements to the Bibliography and Abstracts on Electrical Contacts - 01 January 1954

STP47960S: Introduction - 01 January 1953

STP152-EB: Symposium on Insulating Oils: Fifth Series - 01 January 1953

STP47961S: The Reclamation of Insulating Oils - 01 January 1953

STP56G-EB: Bibliography and Abstracts on Electrical Contacts 1835–1951 - 01 November 1952

STP39242S: A Stable Internal Standard Flame Photometer for Sodium, Potassium, Lithium and Calcium Analyses in Biological Fluids and A Study of Ion Interference - 01 January 1952

STP48079S: Introduction - 01 January 1952

STP135-EB: Symposium on Insulating Oils: Fourth Series - 01 January 1952

STP48081S: Evaluation of Mineral Transformer Oil During Service. Part III: An Examination of Selected Transformers - 01 January 1952

STP48080S: Evaluation of Mineral Transformer Oil During Service. Part II: Correlation of Oil Characteristics with Continued Transformer Operation - 01 January 1952

STP46812S: Ultrasonics in the Electrical Industry - 01 January 1951

STP46732S: Hydrogenizing Effect of Steam on Ferrous Alloys at Elevated Temperatures - 01 January 1951

STP46708S: Operating Experience and Problems Relative to Lubricating Systems of Steam Turbine Sets for Utilities - 01 January 1950

STP105-EB: Symposium on Turbine Oils - 01 January 1950

STP46706S: Introduction - 01 January 1950

STP46709S: Specific Problems Pertaining to Lubrication of Industrial Turbines - 01 January 1950

STP46707S: Lubrication Problems and Requirements of Gas Turbine Equipment - 01 January 1950

STP95-EB: Symposium on Insulating Oils - 01 January 1949

STP43961S: One System of Laboratory Testing to Appraise Serviceability of Oils in Transformers - 01 January 1949

STP43962S: Performance of Inhibited Transformer Oils - 01 January 1949

STP43960S: Performance Characteristics of the Askarels - 01 January 1949

STP44970S: Alloys and Ceramic Materials for High-Temperature Service - 01 January 1946

STP68-EB: Symposium on Materials for Gas Turbines - 01 January 1946

STP44972S: Resistance of Iron-Nickel-Chromium Alloys to Corrosion in Air at 1600 to 2200 F - 01 January 1946

STP44973S: Compressive Properties of Aluminum Alloy Sheet at Elevated Temperatures - 01 January 1946

STP44974S: Tensile and Creep Strengths of Some Magnesium-Base Alloys at Elevated Temperature - 01 January 1946

STP44966S: Heat-Resisting Metals for Gas-Turbine Parts - 01 January 1946

STP44967S: High-Temperature Alloys Developed for Aircraft Turbosuperchargers and Gas Turbines - 01 January 1946

STP44968S: Chromium-Base Alloys - 01 January 1946

STP44969S: Metallurgy of High-Temperature Alloys Used on Current Gas Turbine Designs - 01 January 1946

STP43913S: High-Voltage X-rays in the Boiler Shop - 01 January 1943

STP43914S: The Gamma-Ray Radiography of Welded High Pressure Power Plant Piping - 01 January 1943

STP41384S: Theoretical Analysis of Sodium Removal from Fast Flux Test Facility Fuel Subassemblies - 01 January 1937

STP43861S: Trends in Engineering Requirements for Metals for the Power-Plant Industry - 01 January 1932

STP43862S: Steam Turbine Materials for High Temperatures - 01 January 1932

STP43863S: Metallurgical Requirements for High-Temperature Steam Piping - 01 January 1932