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Digital Library/Symposia/E10/The Effects of Radiation on Materials: 21st International Symposium
Sponsored by ASTM committee E10 on Nuclear Technology and Applications
June 18 2002 - June 20 2002

 Papers Published from this Symposium
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 305335°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
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
 
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