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Corrosion of M5 in PWRs: Quantification of Li, B, H and Nb in the Oxide Layers Formed Under Different Conditions
Studies Regarding Corrosion Mechanisms in Zirconium Alloys
Understanding Crack Formation at the Metal/Oxide Interface During Corrosion of Zircaloy-4 Using a Simple Mechanical Model
Detailed Analysis of the Microstructure of the Metal/Oxide Interface Region in Zircaloy-2 after Autoclave Corrosion Testing
Microstructural Studies of Heat Treated Zr-2.5Nb Alloy for Pressure Tube Applications
Hydrogen Absorption Mechanism of Zirconium Alloys Based on Characterization of Oxide Layer
Ultra Low Tin Quaternary Alloys PWR Performance—Impact of Tin Content on Corrosion Resistance, Irradiation Growth, and Mechanical Properties
Neutron Radiography: A Powerful Tool for Fast, Quantitative and Non-Destructive Determination of Hydrogen Concentration and Distribution in Zirconium Alloys
In Situ Scanning Electron Microscope Observation and Finite Element Method Analysis of Delayed Hydride Cracking Propagation in Zircaloy-2 Fuel Cladding Tubes
ZIRLO^® Irradiation Creep Stress Dependence in Compression and Tension
Experimental Investigation of Irradiation Creep and Growth of Recrystallized Zircaloy-4 Guide Tubes Pre-Irradiated in PWR
Study on the Role of Second Phase Particles in Hydrogen Uptake Behavior of Zirconium Alloys
Effects of Secondary Phase Particle Dissolution on the In-Reactor Performance of BWR Cladding
Damage Build-Up in Zirconium Alloys During Mechanical Processing: Application to Cold Pilgering
Characterization of Oxygen Distribution in LOCA Situations
Polycrystalline Modeling of the Effect of Texture and Dislocation Microstructure on Anisotropic Thermal Creep of Pressurized Zr-2.5Nb Tubes
Improved Zr-2.5Nb Pressure Tubes for Reduced Diametral Strain in Advanced CANDU Reactors
Radiation Damage of E635 Alloy Under High Dose Irradiation in the VVER-1000 and BOR-60 Reactors
Hydrogen Solubility and Microstructural Changes in Zircaloy-4 Due to Neutron Irradiation
Study of the Initial Stage and Anisotropic Growth of Oxide Layers Formed on Zircaloy-4
Statistical Analysis of Hydride Reorientation Properties in Irradiated Zircaloy-2
Multiscale Analysis of Viscoplastic Behavior of Recrystallized Zircaloy-4 at 400°C
Hydride Platelet Reorientation in Zircaloy Studied with Synchrotron Radiation Diffraction
In Situ Studies of Variant Selection During the α-β-α Phase Transformation in Zr-2.5Nb
RIA Failure of High Burnup Fuel Rod Irradiated in the Leibstadt Reactor: Out-of-Pile Mechanical Simulation and Comparison with Pulse Reactor Tests
Impact of Irradiation Damage Recovery During Transportation on the Subsequent Room Temperature Tensile Behavior of Irradiated Zirconium Alloys
Texture Evolution of Zircaloy-2 During Beta-Quenching: Effect of Process Variables
Advanced Zirconium Alloy for PWR Application
Shadow Corrosion-Induced Bow of Zircaloy-2 Channels
Segregation in Vacuum Arc Remelted Zirconium Alloy Ingots
Dynamic Recrystallization in Zirconium Alloys
Explosion Cladding: An Enabling Technology for Zirconium in the Chemical Process Industry
The Development of Zr-2.5Nb Pressure Tubes for CANDU Reactors
REFLET Experiment in OSIRIS: Relaxation under Flux as a Method for Determining Creep Behavior of Zircaloy Assembly Components
Photoelectrochemical Investigation of Radiation-Enhanced Shadow Corrosion Phenomenon
Optimization of Zry-2 for High Burnups
High Temperature Aqueous Corrosion and Deuterium Uptake of Coupons Prepared from the Front and Back Ends of Zr-2.5Nb Pressure Tubes
The Evolution of Microstructure and Deformation Stability in Zr–Nb–(Sn,Fe) Alloys Under Neutron Irradiation
Measurement and Modeling of Second Phase Precipitation Kinetics in Zirconium Niobium Alloys
Simulation of Outside-in Cracking in Boiling Water Reactor Fuel Cladding Tubes under Power Ramp
Performance of Zirconium Alloys in Light Water Reactors with a Review of Nodular Corrosion
Further Results on Attenuation of Neutron Embrittlement Effects in a Simulated RPV Wall
The Effect of Microstructure on Delayed Hydride Cracking Behavior of Zircaloy-4 Fuel Cladding—An International Atomic Energy Agency Coordinated Research Program
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
Practical Challenges Testing Coupons with Residual Stresses from Cold Expanded Holes
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
In PWR Comprehensive Study of High Burn-Up Corrosion and Growth Behavior of M5^® and Recrystallized Low-Tin Zircaloy-4
Stress-Triaxiality in Zr-2.5Nb Pressure Tube Materials
Statistical Analysis of Fatigue Related Microstructural Parameters for Airframe Aluminum Alloys
Effect of Inhomogeneity in Aligned Grains on Creep-Fatigue Crack Opening and Propagation Behavior of Directionally Solidified Superalloy
Investigation of Irradiation Hardening and Embrittlement of Zr-2.5%Nb Alloy with High-Energy (e,γ)-Beams
A Concept for the Fatigue Life Prediction of Components from an Aluminum-Steel Compound
The Significance of a Crack Growth Law for a C(T) Fracture Specimen Undergoing Stable Crack Extension
Towards Crack Arrest Testing Using Miniature Specimens
Investigation of Material Fatigue Behavior Through Cyclic Ball Indentation Testing
Characterization of Local Strain Distribution in Zircaloy-4 and M5^® Alloys
Evaluation of Hydride Reorientation Behavior and Mechanical Properties for High-Burnup Fuel-Cladding Tubes in Interim Dry Storage
Toward a Better Understanding of Dimensional Changes in Zircaloy-4: What is the Impact Induced by Hydrides and Oxide Layer?
Analysis of Material Inhomogeneity in the European Round Robin Fracture Toughness Data Set
In-situ Fatigue Damage Investigations in Welded Metallic Components by Infrared Techniques
Comparison of the Temperature and Pre-Aging Influences on the Low Cycle Fatigue and Thermo-Mechanical Fatigue Behavior of Copper Alloys (CuCoBe/CuCo2Be)
Influence of the Peening Intensity on the Fatigue Behavior of Shot Peened Titanium Components
Test Results from Round Robin on Precracking and CTOD Testing of Welds
Focused Ion Beam as New Tool for Local Investigations of the Interaction of Microcracks with Grain Boundaries
Experimental Study of the Fracture Toughness Transferability to Pressurized Thermal Shock Representative Loading Conditions
Fatigue Crack Growth in Open and Nut-Loaded Bolts with and without Pretension Loading
Carrying Capacity Prediction of Steam Turbine Rotors with Operation Damage
Effects of Surface Morphology and Distributed Inclusions on the Low Cycle Fatigue Behavior of Miniaturized Specimens of F82H steel
Influence of Structure Changes in E110 Alloy Claddings on Ductility Loss Under LOCA Conditions
Determination of Transferable Lower-Bound Fracture Toughness from Small Specimens
Effect of Prestrain on Fatigue Crack Growth of Age-Hardened Al 6061-T6
Impact of Residual Stress and Elastic Follow-Up on Fracture
Influence of Residual Stresses on Fretting Fatigue Life Prediction in Ti-6Al-4V
Elastic-Plastic Finite-Element Analyses of Compression Precracking and Its Influence on Subsequent Fatigue-Crack Growth
Evaluation of Residual Stress Corrections to Fracture Toughness Values
Application of Subsize Specimens for Re-Irradiation Embrittlement Monitoring of the First Generation of VVER-440 RPV Steels
Contribution of Thermodynamic Calculations to Metallurgical Studies of Multi-Component Zirconium Based Alloys
Tearing Crack Growth and Fracture Micro-Mechanisms Under Micro Segregation in Zr-2.5%Nb Pressure Tube Material
Investigation of Structural and Chemical Uniformity of Zr2.5% Nb and E635 Alloy by Radioactive Indicators
ZIRLO^TM Cladding Improvement
In Situ EIS Measurements of Irradiated Zircaloy-4 Post-Transition Corrosion Kinetic Behavior
Laser Generated Crack-Like Features Developed for Assessment of Fatigue Threshold Behavior
An Examination of Fatigue Initiation Mechanisms in Thin 35Co-35Ni-20Cr-10Mo Medical Grade Wires
Compression Precracking to Generate Near Threshold Fatigue Crack Growth Rates in an Aluminum and Titanium Alloy
Analysis of Crack Growth at R=−1 Under Variable Amplitude Loading on a Steel for Railway Axles
Fatigue Response of Aluminum Aircraft Structure under Engineered Residual Stress Processing
Notch Strengthening and Its Impact on the Deformation and Fracture of 316L Stainless Steel
Role of Twinning and Slip in Deformation of a Zr-2.5Nb Tube
Intergranular and Interphase Constraints in Zirconium Alloys
In-Reactor Deformation of Zirconium Alloy Components
Evaluation of Residual Stress Effects on Brittle Fracture Strength Based on Weibull Stress Criterion
Hydrogen/Plasticity Interactions at an Axial Crack in Pipeline Steel
On the quantification of the constraint effect along a three-dimensional crack front
Multi-Scale Approach to the Fatigue Crack Propagation in High-Strength Pearlitic Steel Wires
Impact Fatigue Failure Investigation of HVOF Coatings
Surveillance of the Fracture Behavior of Zircaloy-4 Welds Using the Small Punch Test
Hydrogen Content, Preoxidation, and Cooling Scenario Effects on Post-Quench Microstructure and Mechanical Properties of Zircaloy-4 and M5^® Alloys in LOCA Conditions
CASTA DIVA^®: Experiments and Modeling of Oxide-Induced Deformation in Nuclear Components
Corrosion and Oxide Properties of HANA Alloys
Neutron Response Function for BC-523A Scintillation Detector in the Energy Range 0.5 MeV to 20 MeV
Experimental and Analytical Investigation of the Mechanical Behavior of High-Burnup Zircaloy-4 Fuel Cladding
A New Model to Predict the Oxidation Kinetics of Zirconium Alloys in a Pressurized Water Reactor
Experimental Estimation of J-R Curves from Load-CMOD Record for SE(B) Specimens
Mechanical Evaluation of Mixed As-Cast and Friction Stir Processed Zones in Nickel Aluminum Bronze
Fatigue Behavior of Adhesively Bonded Aluminium Double Strap Joints
A Simplified Modeling Approach for Predicting Global Distortion in Large Metallic Parts Caused by the Installation of Interference Fit Bushings
The Influence of Residual Stresses on the Fatigue Strength of Cold-Formed Structural Tubes
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
Irradiation-Induced Growth and Microstructure of Recrystallized, Cold Worked and Quenched Zircaloy-2, NSF, and E635 Alloys
Investigations of the Microstructure and Mechanical Properties of Prior-β Structure as a Function of the Oxygen Content in Two Zirconium Alloys
Introducing Heterogeneity into Brittle Fracture Modeling of a 22NiMoCr37 Ferritic Steel Ring Forging
Fatigue Crack Growth in Integrally Stiffened Panels Joined Using Friction Stir Welding and Swept Friction Stir Spot Welding
Fretting Fatigue Behavior of Shot-Peened Ti-6Al-4V and IN100
The Influence of Residual Stress on the Design of Aircraft Primary Structure
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
The Effect of Hydrogen on the Transition Behavior of the Corrosion Rate of Zirconium Alloys
Experimental and Modeling Approach of Irradiation Defects Recovery in Zirconium Alloys: Impact of an Applied Stress
Structure-Phase State, Corrosion and Irradiation Properties of Zr-Nb-Fe-Sn System Alloys
Characterization of Zirconium Hydrides and Phase Field Approach to a Mesoscopic-Scale Modeling of Their Precipitation
Microstructural Characterization of Oxides Formed on Model Zr Alloys Using Synchrotron Radiation
Assessing the Loading Rate for a Fracture Toughness Test in the Ductile-to-Brittle Transition Region
Prediction of the Fatigue Limit of Prestrained Carbon Steel Under Tensile Mean Stress
Measurement of Rates of Delayed Hydride Cracking (DHC) in Zr-2.5Nb Alloys—An IAEA Coordinated Research Project
Behavior and Mechanisms of Irradiation—Thermal Creep of Cladding Tubes Made of Zirconium Alloys
Cladding Tube Deformation Test for Stress Reorientation of Hydrides
Effect of Water Chemistry and Composition on Microstructural Evolution of Oxide on Zr Alloys
Effects of Pt Surface Coverage on Oxidation of Zr and Other Materials
Round-Robin Testing of Fracture Toughness Characteristics of Thin-Walled Tubing
Attenuation of Neutron Radiation Damage Through a Simulated RPV Wall
Effect of Irradiation Damage on the Deformation Properties of Zr-2.5Nb Pressure Tubes
Deformation Anisotropy of Annealed Zircaloy-2 as a Function of Fast Neutron Fluence
Microstructure Evolution in Zr Alloys during Irradiation: Dose, Dose Rate, and Impurity Dependence
Fracture Toughness of Hydrided Zircaloy-4 Sheet Under Through-Thickness Crack Growth Conditions
In-Pile Criteria for the Initiation of Massive Hydriding of Zr in Steam-Hydrogen Environment
Determination and Interpretation of Texture Evolution during Deformation of a Zirconium Alloy
Chemistry of Waterside Oxide Layers on Pressure Tubes
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
A Study of the Structure and Chemistry in Zircaloy-2 and the Resulting Oxide After High Temperature Corrosion
Mechanical Properties of Zr-2.5Nb Pressure Tubes Made from Electrolytic Powder
Manufacturing Variability, Microstructure, and Deformation of Zr-2.5Nb Pressure Tubes
Effect of Local Hydride Accumulations on Zircaloy Cladding Mechanical Properties
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
Studies of Corrosion of Cladding Materials in Simulated BWR Environment using Impedance Measurements
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
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
The Validity of the Use of Equivalent DIDO Nickel Dose for Graphite Dosimetry
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
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
Modeling of the Simultaneous Evolution of Vacancy and Interstitial Dislocation Loops in hcp Metals Under Irradiation
Phase Composition, Structure, and Plastic Deformation Localization in Zr1%Nb alloys
Radiation-Induced Stress Relaxation of Welded Type 304 Stainless Steel Evaluated by Neutron Diffraction
Effect of Alloying Elements and Impurities on in-BWR Corrosion of Zirconium Alloys
Comparison of the High Burn-Up Corrosion on M5 and Low Tin Zircaloy-4
Thermal Creep of Irradiated Zircaloy Cladding
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
The Effect of Duplex Cladding Outer Component Tin Content on Corrosion, Hydrogen Pick-up, and Hydride Distribution at Very High Burnup
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
Effect of Irradiation on the Fracture Properties of Zr-2.5Nb Pressure Tubes at the End of Design Life
The Effect of Liner Component Iron Content on Cladding Corrosion, Hydriding, and PCI Resistance
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
Destruction of Crystallographic Texture in Zirconium Alloy Tubes
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
Plastic Deformation of Irradiated Zirconium Alloys: TEM Investigations and Micro-Mechanical Modeling
Influence of Structure—Phase State of Nb Containing Zr Alloys on Irradiation-Induced Growth
Delayed Hydrogen Cracking Velocity and J-Integral Measurements on Irradiated BWR Cladding
Fretting-Wear Behavior of Zircaloy-4, OPTIN™, and ZIRLO™ Fuel Rods and Grid Supports Under Various Autoclave and Hydraulic Loop Endurance Test Conditions
Neutron Flux Effect on the Irradiation Hardening of Type 304 Stainless Steel
Microstructural Stability of M5™ Alloy Irradiated up to High Neutron Fluences
Temperature and Strain Rate Effects on Zr-1%Nb Alloy Deformation
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
Damage Dependence of Irradiation Deformation of Zr-2.5Nb Pressure Tubes
Recent Surveillance Data and a Revised Embrittlement Correlation
Extrapolation of Fracture Toughness Data for HT9 Irradiated at 360–390°C
The Effect of Beta-Quenching in Final Dimension on the Irradiation Growth of Tubes and Channels
Improved ZIRLO^TM Cladding Performance through Chemistry and Process Modifications
Shadow Corrosion Mechanism of Zircaloy
TEM Examinations of the Metal-Oxide Interface of Zirconium Based Alloys Irradiated in a Pressurized Water Reactor
Failure of Hydrided Zircaloy-4 Under Equal-Biaxial and Plane-Strain Tensile Deformation
Mechanical Properties of Zircaloy-4 PWR Fuel Cladding with Burnup 54-64MWd/kgU and Implications for RIA Behavior
On Secondary β-Nb Phase Precipitation within Primary α-Zr Phase in Zr-Nb Alloys During Tensile Deformation
Study of Nb and Fe Precipitation in α-Phase Temperature Range (400 to 550°C) in Zr-Nb-(Fe-Sn) Alloys
Predicting Oxidation and Deuterium Ingress for Zr-2.5Nb CANDU Pressure Tubes
In-Core Tests of Effects of BWR Water Chemistry Impurities on Zircaloy Corrosion
Microstructure and Growth Mechanism of Oxide Layers Formed on Zr Alloys Studied with Micro-Beam Synchrotron Radiation
Ductility of Zircaloy-4 Fuel Cladding and Guide Tubes at High Fluences
Microstructure and Phase Control in Zr-Fe-Cr-Ni Alloys: Thermodynamic and Kinetic Aspects
Inhibitors for Reducing Hydrogen Ingress During Corrosion of Zirconium Alloys
Overload Fracture of Flaw Tip Hydrides in Zr-2.5Nb Pressure Tubes
In-Situ Studies of the Oxide Film Properties on BWR Fuel Cladding Materials
Review of Deformation Mechanisms, Texture, and Mechanical Anisotropy in Zirconium and Zirconium Base Alloys
Simulation of Cold Pilgering Process by a Generalized Plane Strain FEM
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
Use of the Irradiation-Thermal Creep Model of Zr-1% Nb Alloy Cladding Tubes to Describe Dimensional Changes of VVER Fuel Rods
Creep-Fatigue Behavior in High Strength Copper Alloys
Influence of Long Service Exposures on the Thermal-Mechanical Behavior of Zy-4 and M5™ Alloys in LOCA Conditions
Tensile, Flexural, and Shear Properties of Neutron Irradiated SiC/SiC Composites with Different Fiber-Matrix Interfaces
ZIRLO™ — An Alloy Development Success
The Correlation Between Microstructures and in-BWR Corrosion Behavior of Highly Irradiated Zr-based Alloys
Plutonium-238 Alpha-Decay Damage Study of A Glass-Bonded Sodalite Ceramic Waste Form
Role of Iron for Hydrogen Absorption Mechanism in Zirconium Alloys
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
Identification of Crystalline Behavior on Macroscopic Response and Local Strain Field Analysis: Application to Alpha Zirconium Alloys
Effect of Fabrication Variables on Irradiation Response of Crack Growth Resistance of Zr-2.5Nb
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
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