Nuclear, Solar, and Geothermal Energy

    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

    Comparison of Regulatory Guide 1.99 Fluence Attenuation Methods

    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

    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

    The Power Distribution and Neutron Fluence Measurements and Calculations in the VVER-1000 Mock-Up on the LR-0 Research Reactor

    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

    A Feasibility Study to Determine Cooling Time and Burnup of Advanced Test Reactor Fuel Using a Nondestructive Technique and Three Types of Gamma-ray Detectors

    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

    Boiling Heat Transfer: An Overview of Longstanding and New Challenges

    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)93Nbm 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