Technical Committees / Committee E10 / Committee Publications

Journal of ASTM International

• EPR/PTFE Dosimetry for Test Reactor Environments
• A Broad-Group Cross-Section Library Based on ENDF/B-VII.0 for Fast Neutron Dosimetry Using the CPXSD Methodology
• Development and Testing of the VITAMIN-B7/BUGLE-B7 Coupled Neutron-Gamma Multigroup Cross-Section Libraries
• Reactor Dosimetry and RPV Life Management
• Development of an Active Detector for the Characterization of the Late-Time Radiation Environment from a Reactor Pulse
• Neutron Flux Reduction Programs for Reactor Pressure Vessel of Korea Nuclear Unit 1
• Characterization of the Master Curve Based Fracture Toughness of ORNL TSE5 Steel and Unirradiated and Irradiated ASTM A203D 3.5 % Ni Steel by the IGCAR Procedure
• Analysis of the Notch Effect in Fatigue
• A Three-Dimensional Methodology for the Assessment of Neutron Damage and Nuclear Energy Deposition in Graphite Components of Advanced Gas-Cooled Reactors
• Sensitivity studies associated with dosimetry experiment interpretation
• Measurements of Actinide-Fission Product Yields in Caliban and Prospero Metallic Core Reactor Fission-Neutron Fields
• Uncertainty-Accounted Calculational–Experimental Approach for Improved Conservative Evaluations of VVER RPV Radiation Loading Parameters
• Application of Ex-vessel Neutron Dosimetry Combined with In-core Measurements for Correction of Neutron Source Used for Reactor Pressure Vessel Fluence Calculations
• Development and Experimental Validation of a Calculation Scheme for Nuclear Heating Evaluation in the Core of the OSIRIS Material Testing Reactor
• Ex-Vessel Neutron Dosimetry Analysis for Westinghouse 4-Loop XL Pressurized Water Reactor Plant Using 3D Parallel Discrete Ordinates Code RAPTOR-M3G
• Dosimetry Analyses of the Ringhals 3 and 4 Reactor Pressure Vessels
• Sensitivity of Adjustment to Parameter Correlations and to Response-Parameter Correlations
• Exposure Conditions of Reactor Internals of Rovno VVER-440 Nuclear Power Plant Units 1 and 2
• An Alternative Calibration Method for Counting P-32 Reactor Monitors
• Fitting Method for Spectrum Deduction in High-Energy Neutron Field Induced by GeV-Protons Using Experimental Reaction-Rate Data
• Apparatus for Use in Evaluating Protection from Low Pressure Hot Water Jets
• Path Forward for Dosimetry Cross Sections
• Updating and Extending the IRDF-2002 Dosimetry Library
• Jules Horowitz Reactor, a New Irradiation Facility: Improving Dosimetry for the Future of Nuclear Experimentation
• VVER-440 and VVER-1000 Reactor Dosimetry Benchmark —BUGLE-96 Versus ALPAN VII.0
• Modernization of Existing VVER-1000 Surveillance Programs
• Evaluation of the Structural Sealant for Use in a Four-Sided Structural Sealant Glazing Curtain-Wall System for a Hospital Building
• Structure Transformations in Multicomponent Amorphous Alloys in Connection with Grain-Boundary Segregations and Temper Embrittlement of Steels
• Removal of Heavy Metals (Cu, Pb, and Zn) from Contaminated Sediment Using a Flotation Technique
• Use of Cement-Treated Lightweight Soils Made from Dredged Clay
• Benchmarking of Neutron Production of Heavy-Ion Transport Codes
• Comparison between Hybrid III Headforms by Linear and Angular Dynamic Impact Response Characteristics
• Calculation of Kobasko's Simplified Heat Transfer Coefficients from Cooling Curve Data Obtained with Small Probes
• Application of Different Nuclides in Retrospective Dosimetry
• Dosimetry of the Decommissioned High-Flux Beam Reactor at Brookhaven Lab
• Design and Testing of a Boron Carbide Capsule for Spectral Tailoring in Mixed-Spectrum Reactors
• Los Alamos National Laboratory Fission Basis
• 2010 Review of Neutron and Non-neutron Nuclear Data
• Neutron and Gamma Field Investigations in the VVER-1000 Mock-Up Concrete Shielding on the Reactor LR-0
• New Experimental Proposal for ²³⁵U PFNS Measurement to Answer a Fifty Year Old Question
• The Current Status of the Shielding Integral Benchmark Archive and Database (SINBAD)
• Development of Neutron Measurement in Intense Gamma Field Using New Type of Nuclear Emulsion
• The Fast Neutron Fluence and the Activation Detector Activity Calculations Using the Effective Source Method and the Adjoint Function
• Analysis of Gamma-Ray Dosimetry Experiments in the Zero Power MINERVE Facility
• New Measurements and the Associated Unfolding Methodologies to Characterize the Caliban Pulsed Reactor Cavity Neutron Spectrum by the Foil Activation Method
• VENUS-F: A First Fast Lead Critical Core for Benchmarking
• The Neutron Standard Fields at the BR1 Reactor at SCK•CEN
• CALMOS: Innovative Device for the Measurement of Nuclear Heating in Material Testing Reactors
• Neutron Flux Measurements in the Side-Core Region of Hunterston B Advanced Gas-Cooled Reactor
• Analysis of Dosimetry from the H. B. Robinson Unit 2 Pressure Vessel Benchmark Using RAPTOR-M3G and ALPAN
• A New Formulation of the Unified Monte Carlo Approach (UMC-B) and Cross-Section Evaluation for the Dosimetry Reaction ⁵⁵Mn(n,γ)⁵⁶Mn
• Retrospective Dosimetry Analyses of Reactor Vessel Cladding Samples
• Korean Standard Nuclear Plant Ex-Vessel Neutron Dosimetry Program Ulchin 4
• A New Technique for Dosimetry Reaction Cross-Section Evaluation
• Modeling Vertical Subcooled Boiling Flows at Low Pressures
• Effects of Secondary Phase Particle Dissolution on the In-Reactor Performance of BWR Cladding
• Further Results on Attenuation of Neutron Embrittlement Effects in a Simulated RPV Wall
• Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Materials
• Kinetic Monte Carlo Simulation of Helium-Bubble Evolution in ODS Steels
• Magnox Steel Reactor Pressure Vessel Monitoring Schemes—An Overview
• Influence of Neutron Irradiation on Energy Accumulation and Dissipation during Plastic Flow and Hardening of Metallic Polycrystals
• Interrelationship between True Stress–True Strain Behavior and Deformation Microstructure in the Plastic Deformation of Neutron-Irradiated or Work-Hardened Austenitic Stainless Steel
• Irradiation-Induced Hardening and Embrittlement of High-Cr ODS Ferritic Steels
• Irradiation-Induced Grain-Boundary Solute Segregation and Its Effect on Ductile-to-Brittle Transition Temperature in Reactor Pressure Vessel Steels
• 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
• Study of Microstructure and Property Changes in Irradiated SS316 Wrapper of Fast Breeder Test Reactor
• Unusual Enhancement of Ductility Observed During Evolution of a “Deformation Wave” in 12Cr18Ni10Ti Stainless Steel Irradiated in BN-350
• International Atomic Energy Agency Coordinated Research Projects on Structural Integrity of Reactor Pressure Vessels
• Microstructural Characterization of RPV Materials Irradiated to High Fluences at High Flux
• Effect of Ta Rich Inclusions and Microstructure Change During Precracking on Bimodal Fracture of Reduced-Activation Ferritic/Martensitic Steels Observed in Transition Range
• Investigation of Beltline Welding Seam of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel
• Analysis of the Belgian Surveillance Fracture Toughness Database Using Conventional and Advanced Master Curve Approaches
• Comparison of CANDU Fuel Bundle Finite Element Model with Unirradiated Mechanical Load Experiments
• Towards Crack Arrest Testing Using Miniature Specimens
• Investigation of Material Fatigue Behavior Through Cyclic Ball Indentation Testing
• Effects of Surface Morphology and Distributed Inclusions on the Low Cycle Fatigue Behavior of Miniaturized Specimens of F82H steel
• Determination of Transferable Lower-Bound Fracture Toughness from Small Specimens
• Application of Subsize Specimens for Re-Irradiation Embrittlement Monitoring of the First Generation of VVER-440 RPV Steels
• Notch Strengthening and Its Impact on the Deformation and Fracture of 316L Stainless Steel
• Surveillance of the Fracture Behavior of Zircaloy-4 Welds Using the Small Punch Test
• Neutron Response Function for BC-523A Scintillation Detector in the Energy Range 0.5 MeV to 20 MeV
• Track Detector Measurements in RPV of WWER-1000 Mock-Up in the LR-0 Reactor
• Fracture Toughness Evaluation of Eurofer97 by Testing Small Specimens
• Application of the Small-Punch Test to Irradiated Reactor Vessel Steels in the Brittle-Ductile Transition Region
• Application of Digital Marker Extensometry to Determine the True Stress-Strain Behavior of Irradiated Metals and Alloys
• Miniature Compact Tension Specimens for Upper Shelf Fracture Toughness Measurements on RPV Steels
• Application of Subsize Specimens for Irradiation Embrittlement Monitoring of VVER-440/213 RPV Steels
• Using Subsize Impact Bend Specimens for Estimation of Irradiation and Re-Irradiation Embrittlement of VVER RPV Steels
• Crack Arrest Testing Using Small Wide Plate SE(T) Specimens
• Attenuation of Neutron Radiation Damage Through a Simulated RPV Wall
• Accurate Determination and Benchmarking of Radiation Field Parameters, Relevant for Pressure Vessel Monitoring—Review of Some REDOS Project Results
• Microstructural Features in Aged Erbium Tritide Films
• Use of KLST-Type Miniature Charpy Specimens for Measuring Dynamic Fracture Toughness under Impact Loading Rates
• Kinetics of the Migration and Clustering of Extrinsic Gas in bcc Metals
• The Feasibility of Using a Risk-informed Approach for Calculating Reactor Pressure Vessel Heatup and Cooldown Operating Curves
• Master Integrated Reactor Vessel Surveillance Program
• Specimen Size Limitations in J-R Curve Testing—Standards Versus Reality
• Strain Hardening During Mechanical Twinning and Dislocation Channeling in Irradiated 316 Stainless Steels
• Phosphorus Segregation and Intergranular Embrittlement in Thermally Aged and Neutron Irradiated Reactor Pressure Vessel Steels
• Radiation Embrittlement of Cr–Ni–Mo and Cr–Mo RPV Steels
• DD Simulations of Dislocation-Crack Interaction During Fatigue
• Grain Growth in Nanocrystalline Metal Thin Films under In Situ Ion-Beam Irradiation
• Information Fusion Embrittlement Models for U.S. Power Reactor Pressure Vessel Steels
• Irradiation Hardening and Microstructure Evolution of Ion-irradiated ODS Ferritic Steels
• Analysis of the Ductile-to-Brittle Transition Temperature Shift in a Commercial Power Plant With High Nickel Containing Weld Material
• Modelling of Radiation Damage in Fe-Cr Alloys
• Modeling the Interaction of Helium with Dislocations and Grain Boundaries in Alpha-Iron
• A New Derivation of the Perturbation Operator Used in MCNP
• Application of a Silicon Calorimeter in Fast Burst Reactor Environments
• Monitoring of Radiation Embrittlement of the First and Second Generation of VVER RPV Steels
• Mesh Tally Radiation Damage Calculations and Application to the SNS Target System
• Use of CPXSD for Generation of Effective Fast Multigroup Libraries for Pressure Vessel Fluence Calculations
• Digital Multiparameter System for Characterizing the Neutron-Gamma Field in the LR-O Experimental Reactor
• 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
• Retrospective Dosimetry of Fast Neutrons Focused on the Reactions ⁹³Nb(n,n^′)⁹³Nb^m and ⁵⁴Fe(n,p)⁵⁴Mn
• Internal Probe to Detect Defects from Cascades—In-situ Ion Irradiation Experiments Revisited
• Investigation of Radiation Transport Modeling Trends in the WSMR Fast Burst Reactor Environments
• Measurement of Helium Generation in AISI 304 Reflector and Blanket Assemblies after Long-term Irradiation in EBR-II
• Analysis of the VENUS-3 PWR Pressure Vessel Surveillance Benchmark Using TRIPOLI-4.3 Monte Carlo Code
• An Approach to Determining the Uncertainty in Reactor Test Objects Using Deterministic and Monte Carlo Methods
• Measurement and Calculation of WWER-440 Pressure Vessel Templates Activity for Support of Vessel Dosimetry
• Development of a Silicon Calorimeter for Dosimetry Applications in a Water-Moderated Reactor
• Influence of the Multigroup Approximation on VVER-1000 RPV Neutron/Gamma Flux Calculation
• Reactor Dosimetry Study of the Rhode Island Nuclear Science Center
• The Validity of the Use of Equivalent DIDO Nickel Dose for Graphite Dosimetry
• A New Methodology for Adjustment of Iron Scattering Cross Sections Using Time-of-Flight Spectroscopy
• Coupled Neutron-Gamma Calculations for the LR-0 Experimental Benchmark
• A Light-Water-Cooled Nuclear Reactor of Natural Uranium and Beryllium
• Characterization of Neutron Fields Using MCNP in the Experimental Fast Reactor JOYO
• Benchmark Experiments/Calculations of Neutron Environments in the Annular Core Research Reactor
• TRIM Modeling of Displacement Damage in SiC for Monoenergetic Neutrons
• Characterizing the Time- and Energy-Dependent Reactor n/γ Environment
• Precision Neutron Total Cross-Sectional Measurements for Natural Carbon at Reactor Neutron-Filtered Beams
• Comparison of the Results of the Calculational and Experimental VVER-440 Pressure Vessel Dosimetry at Paks NPP
• Neutron Damage in SiC Semiconductor Radiation Detectors in the GT-MHR
• Measurements and Monte Carlo Calculations of Gamma and Neutron Flux Spectra Inside and Behind Iron/Steel/Water Configurations
• Feasibility Study on a Simple Method of Retrospective Neutron Dosimetry for Reactor Internals and Reactor Vessel
• Benchmarking of PENTRAN-SSN Parallel Transport Code and FAST Preconditioning Algorithm Using the VENUS-2 MOX-Fueled Benchmark Problem
• A Beam-Monitor System for Neutrons and Gamma Rays in the Medical Irradiation Facility of the Kyoto University Research Reactor
• Generalized Linear Least-Squares Adjustment, Revisited
• Spallation Radiation Damage Calculations and Database: Cross-Section Discrepancies between the Codes
• Proton Induced Activation in Mercury: Comparison of Measurements and Calculations
• Radiation Dosimetry in the BNCT Patient Treatment Room at the Brookhaven Medical Research Reactor
• Characterization of the Neutron Field in the HSSI Reusable Irradiation Facility at the Ford Nuclear Reactor
• Survey of the Latest Evaluated Nuclear Data
• Coarse-Mesh Adjoint Biasing of a Monte Carlo Dose Calculation
• Calculation of Neutron Fluxes for Radioactive Inventory Assessment of Magnox Power Plant
• Evaluation of Diamond Detectors for Fast Neutron Fluence Measurements in WWER-1000 Surveillance Assemblies
• Shielding Calculations for the Upgrade of the HFIR HB 2 Beam Line
• Dynamic Finite Element Modeling of Fracture in Charpy V-Notch Specimens of Weld Material 72W
• Attenuation of Radiation Damage and Neutron Field in Reactor Pressure Vessel Wall
• Microstructure Evolution in ZrC Irradiated with Kr ions
• Reactor Dosimetry Issues During Justification of Extension of Service Life of Nonrestorable Equipment of Russian VVER
• Retrospective Measurement of Neutron Activation within the Pressure Circuit Steelwork of a Magnox Reactor and Comparison with Prediction
• Deterministic and Monte Carlo Neutron Transport Calculation for Greifswald-1 and Comparison with Ex-vessel Measured Data
• The Neutron Spectrum of NBS-1
• Sensitivity Analysis and Neutron Fluence Adjustment for VVER-440 RPV
• An International Evaluation of the Neutron Cross Section Standards
• Extensive Revision of the Kernel-based PREVIEW Program and Its Input Data
• Spent Fuel Monitoring with Silicon Carbide Semiconductor Neutron/Gamma Detectors
• Verification of MultiTrans Calculations by the VENUS-3 Benchmark Experiment
• Neutron and Photon Dosimetry at the LR-0 Reactor Using Paired Detectors
• Determination of Adjusted Neutron Spectra in Different MUSE Configurations by Unfolding Techniques
• Fast Neutron Dosimetry and Spectrometry Using Silicon Carbide Semiconductor Detectors
• Benchmark on the 3-D VENUS-2 MOX-Fueled Reactor Dosimetry Calculations by DANTSYS Code System
• Dosimetry Requirements for Pressure Vessel Steels Toughness Curve in the Ductile to Brittle Range
• Advances in Calculation of Fluence to Reactor Structures
• 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
• Comparison of Predicted and Measured Helium Production in U.S. BWR Reactors
• Validation of the Neutron Fluence Calculation on the VVER-440 RPV Support Structure
• Low Strain-Rate Microstructural Deformation Behavior in 316 Stainless Steel Irradiated in EBR-II
• Use of Broken Charpy V-notch Specimens from a Surveillance Program for Fracture Toughness Determination
• The Effect of Joint Condition on Mechanical Properties of Irradiated Hot Isostatic Pressed Joints
• Reactor Dosimetry with Niobium
• Gas Production in Reactor Materials
• Mechanical Property Changes in Reactor Vessel Materials Thermally Aged for 209 000 H at 260°C
• Radiation-Induced Stress Relaxation of Welded Type 304 Stainless Steel Evaluated by Neutron Diffraction
• Flow Localization Processes in Austenitic Alloys
• Microstructural and Mechanical Characterization of Radiation Effects in Model Reactor Pressure Vessel Steels
• Effects of Neutron Irradiation on Precipitation in Reactor Pressure Vessel Steels
• Deformation Mechanism Maps of Unirradiated and Irradiated V-4Cr-4Ti
• Small Angle Neutron Scattering Study of Irradiated Martensitic Steels: Relation Between Microstructural Evolution and Hardening
• Atomic-Scale Simulation of Defect Cluster Formation in High-Energy Displacement Cascades in Zirconium
• Effects of Proton Irradiation on Reactor Pressure Vessel Steel and Its Model Alloys
• Fracture Toughness, Thermo-Electric Power, and Atom Probe Investigations of JRQ Steel in I, IA, IAR, and IARA Conditions
• 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
• Mechanical Properties of Cubic Silicon Carbide after Neutron Irradiation at Elevated Temperatures
• Radiation Resistance of Advanced Ferritic-Martensitic Steel HCM12A
• Radiation- and Thermally-Induced Phosphorus Inter-Granular Segregation in Pressure Vessel Steels
• Correlated Formation and Stability of SIA Loops and Stacking Fault Tetrahedra in High Energy Displacement Cascades in Copper
• Neutron Flux Effect on the Irradiation Hardening of Type 304 Stainless Steel
• New Chemical Antistripping Additives for Bituminous Mixtures
• Which Way Do Concrete Cracks Run?
• Biocomposites: Exploring Surface Texture for Cell Adhesion
• Development of Fuel Clad Materials for High Burn-up Operation of LWR
• Modeling the Effects of Oversize Solute Additions on Radiation-Induced Segregation in Austenitic Stainless Steels
• Recent Surveillance Data and a Revised Embrittlement Correlation
• Extrapolation of Fracture Toughness Data for HT9 Irradiated at 360–390°C
• Behavior of Irradiated Type 316 Stainless Steels under Low-Strain-Rate Tensile Conditions
• The Role of Grain Boundary Engineering on the High Temperature Creep of Ferritic-Martensitic Alloy T91
• Assessment of Neutron Irradiation-Induced Grain Boundary Embrittlement by Phosphorous Segregation in a Reactor Pressure Vessel Steel
• Effects of Neutron Dose, Dose Rate, and Irradiation Temperature on the Irradiation Embrittlement of a Low-Copper Reactor Pressure Vessel Steel
• Creep-Fatigue Behavior in High Strength Copper Alloys
• Tensile, Flexural, and Shear Properties of Neutron Irradiated SiC/SiC Composites with Different Fiber-Matrix Interfaces
• Plutonium-238 Alpha-Decay Damage Study of A Glass-Bonded Sodalite Ceramic Waste Form
• Microstructure Response in Copper and Copper Alloys Irradiated with Fission Neutrons with Controlled Temperature Variations
• Properties of 20% Cold-Worked 316 Stainless Steel Irradiated at Low Dose Rate
• Creep Deformation in V-4Cr-4Ti in a Low-Oxygen Lithium Environment
• Fracture Toughness and Atom Probe Characterization of a Highly Embrittled RPV Weld
• Effect of Stress Relief Time on the Transition Temperature of Linde 80 Welds
• Irradiation Creep and Swelling of Russian Ferritic-Martensitic Steels Irradiated to Very High Exposures in the BN-350 Fast Reactor at 305–335°C
• Grain Boundary Phosphorous Segregation and Its Influence on the Ductile Brittle Transition Temperature in Reactor Pressure Vessel Steels
• New Methodologies for Developing Radiation Embrittlement Models and Trend Curves of the Charpy Impact Test Data
• Fatigue Response and Life Prediction of Selected Reactor Materials
• Effect of Heat Treatment and Tantalum on Microstructure and Mechanical Properties of Fe-9Cr-2W-0.25V Steel
• Microstructural Aspects of Irradiation Damage in A508 Gr 4N Forging Steel: Composition and Flux Effects
• Erratum/Correction to: Investigation of Burning Iron in Oxygen-Enriched Atmospheres through Microanalysis Techniques
• Critical Review of Through-Wall Attenuation of Mechanical Properties in RPV Steels
• Martensitic Transformations in Neutron Irradiated and Helium Implanted Stainless Steels
• Effect of Ion Irradiation on Microstructure and Hardness in Zircaloy-4
• The Role of Fine Defect Clusters in Irradiation-Assisted Stress Corrosion Cracking of Proton-Irradiated 304 Stainless Steel
• 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
• Dependence of Re-embrittlement Rate After Annealing on the Copper, Nickel and Phosphorus Contents in Model Alloys
• The Effect of Neutron Flux on Radiation-Induced Embrittlement in Reactor Pressure Vessel Steels
• Surprisingly Large Generation and Retention of Helium and Hydrogen in Pure Nickel Irradiated at High Temperatures and High Neutron Exposures
• Stress and Temperature Dependence of Irradiation Creep of Selected FCC and BCC Steels at Low Swelling