Effects of Radiation on Materials |
Contents
Properties of 20 ColdWorked 316 Stainless Steel Irradiated at Low Dose Rate | 3 |
Study on Ductile Fracture Strain and Fracture Toughness of Irradiated Austenitic Stainless Steels | 15 |
Investigation of Microstructure and Mechanical Properties of 18Cr10NiTi Steel Irradiated in the Core of V VER1000 Reactor | 32 |
Influence of Oversized Solute Additions on RadiationInduced Microstructure and Microchemistry in Austenitic Stainless Steel | 46 |
Solute Addition Effect for Fe15Cr20Ni Austenitic Steels Irradiated in Joyo | 56 |
The Effect of Void Swelling on Electrical Resistance and Elastic Moduli in Austenitic Steels | 66 |
The Role of Fine Defect Clusters in IrradiationAssisted Stress Corrosion Cracking of ProtonIrradiated 304 Stainless Steel | 78 |
The Effect of Hardening Source in Proton IrradiationAssisted Stress Corrosion Cracking of Cold Worked Type 304 Stainless Steel | 92 |
Incubation Period for Void Swelling and Its Dependence on Temperature Dose Rate and Dislocation Structure Evolution | 418 |
Determination of the Lower Temperature Limit of Void Swelling of Stainless Steels at PWRRelevant Displacement Rates | 429 |
Dependence of Maximum Swelling Temperature on Damage Dose in Cold Worked 16Cr15Ni2Mo1Mn Cladding Irradiated in BN600 | 446 |
Stress and Temperature Dependence of Irradiation Creep of Selected FCC and BCC Steels at Low Swelling | 454 |
Irradiation Creep and Swelling of Russian FerriticMartensitic Steels Irradiated to Very High Exposures in the BN350 Fast Reactor at 305335C | 468 |
Kinetics of Helium Bubble Formation in Nuclear and Structural Materials | 479 |
Bubble Microstructures in Helium Injected Palladium Foils | 492 |
Fatigue Response and Life Prediction of Selected Reactor Materials | 502 |
Martensitic Transformations in Neutron Irradiated and Helium Implanted Stainless Steels | 105 |
Fracture Toughness and Atom Probe Characterization of a Highly Embrittled RPV Weld | 123 |
On the Mechanism of Irradiation Embrittlement Enhancement in Reactor Pressure Vessel Steels at High Neutron Fluences | 138 |
Irradiation and PostAnnealing Reirradiation Effects on Fracture Toughness of RPV Steel Heat JRQ | 149 |
Dependence of Reembrittlement Rate After Annealing on the Copper Nickel and Phosphorus Contents in Model Alloys | 164 |
Evaluation of Irradiation Embrittlement of A508 Gr 4N and Comparison to Other LowAlloy Steels | 179 |
Composition and Flux Effects | 194 |
Effect of Stress Relief Time on the Transition Temperature of Linde 80 Welds | 208 |
Critical Review of ThroughWall Attenuation of Mechanical Properties in RPV Steels | 221 |
A MechanisticallyGuided Charpy Embrittlement Correlation for Reactor Pressure Vessel Integrity Assessment | 247 |
Development of RPV Embrittlement Evaluation Technology for Charpy Upper Shelf Region | 266 |
Master Curve of Irradiated JRQ Material | 277 |
Development of International Guidelines for Application of the Master Curve Approach to Reactor Pressure Vessel Integrity | 289 |
The Technical Foundations of a Unified Adjusted Reference Temperature for RPV Fracture Toughness | 300 |
A Statistical Analysis of the Effect of Neutron Irradiation Dose and Dose Spectrum on Changes of Charpy Impact Energy for CMn Steels | 311 |
The Effect of Neutron Flux on Radiationinduced Embrittlement in Reactor Pressure Vessel Steels | 326 |
Hardening Mechanisms in FerriticMartensitic Steels | 341 |
Effects of Copper Content on the Tensile Properties of IronCopper Alloys | 352 |
Irradiation Hardening and Microstructural Evolution in FeCu Model Alloys | 365 |
Effect of Heat Treatment and Tantalum on Microstructure and Mechanical Properties of Fe9Cr2W 025V Steel | 376 |
Oxide Particle Stability in Oxide Dispersion Strengthened Ferritic Steels During Neutron Irradiation | 391 |
Examination of Postirradiation Deformation Microstructures in F82H | 401 |
Fracture Toughness Characterization of Irradiated F82H in the Transition Region | 408 |
Detection of RadiationEnhanced Diffusion by Means of NeutronIrradiated Diffusion Couples of FeCrNi System | 516 |
Surprisingly Large Generation and Retention of Helium and Hydrogen in Pure Nickel Irradiated at High Temperatures and High Neutron Exposures | 529 |
The Influence of Prelrradiation Heat Treatments on Thermal NonEquilibrium and RadiationInduced Segregation Behavior in Model Austenitic Stainl... | 540 |
laterGranular Phosphorus Segregation in Ferritic Steels | 553 |
Grain Boundary Phosphorous Segregation and Its Influence on the Ductile Brittle Transition Temperature in Reactor Pressure Vessel Steels | 565 |
The Modeling of RadiationInduced Phosphorus Segregation at Point Defect Sinks in Dilute FeP Alloys | 579 |
Irradiation Induced VacancyCu Aggregations in FeCu Model Alloys of Reactor Pressure Vessel Steels Studied by Positron Annihilation | 590 |
Heavy Ion Fiuence Measurements Based on Radiation Effects Generated in CTA Foils | 604 |
Tensile Property Estimates Obtained Using a Low Compliance Shear Punch Test Fixture | 612 |
Revisiting the Use of SiC as a Post Irradiation Temperature Monitor | 623 |
New Methodologies for Developing Radiation Embrittlement Models and Trend Curves of the Charpy Impact Test Data | 634 |
Mechanical and Structural Property Changes of Monolithic SiC and Advanced SiCSiC Composites due to Low Temperature He+lon Irradiation and P... | 655 |
Precipitation and Amorphization in Boron Carbide Irradiated by High Energy Helium Ions | 670 |
Effects of Pu Decay on a Sodalite Based Ceramic Waste Form | 680 |
Changes in Mechanical Properties of HighPurity V4Cr4Ti Si AI Y Alloys after Neutron Irradiation at Relatively Low Temperatures | 692 |
Creep Deformation in V4Cr4Ti in a LowOxygen Lithium Environment | 702 |
Varying Temperature Irradiation Effects of V4Cr4Ti Alloy with Small Addition of Si Ai and Y | 714 |
Peculiarities of Structural and Behavioral Changes of Some Zirconium Alloys at Damage Doses of Up to 50 dpa | 727 |
Effect of Ion Irradiation on Microstructure and Hardness in Zircaloy4 | 741 |
Microstructure Response in Copper and Copper Alloys Irradiated with Fission Neutrons with Controlled Temperature Variations | 753 |
Author Index | 763 |
767 | |
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Common terms and phrases
316 stainless steel A. S. Kumar annealing ASTM International ASTM STP atoms austenitic austenitic stainless steels behavior BN-350 reactor bubble Charpy impact clusters composition copper correlation crack damage dose DBTT deformation diffusion dislocation loops dose rate ductile EBR-II Effects of Radiation electrical resistance electron elongation embrittlement energy experimental Figure fluence flux fracture toughness Gr 4N grain boundary helium increase International Symposium interstitial irradiation conditions irradiation embrittlement irradiation hardening irradiation temperature irradiation-induced Journal of Nuclear M. L. Grossbeck Master Curve matrix measured microstructure model alloys n/m² neutron fluence neutron irradiation nickel Nuclear Materials observed parameters phosphorus point defect precipitates predicted Pressure Vessel Steels proton Radiation on Materials Reactor Pressure Vessel samples segregation shown in Fig stainless steel steel irradiated surveillance T. R. Allen tensile properties thermal transition temperature transmission electron microscopy tubes unirradiated vacancy values West Conshohocken yield strength Zircaloy