Digital Library / Topics / Nuclear, Solar, and Geothermal Energy / All JAI

• 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
• A Light-Water-Cooled Nuclear Reactor of Natural Uranium and Beryllium
• Characterization of Neutron Fields Using MCNP in the Experimental Fast Reactor JOYO
• 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
• 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