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SEDL / STP / STP1475-EB
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STP1475
Effects of Radiation on Materials: 22nd Symposium
Allen TR, Lott RG, Busby JT, Kumar AS
Pages: 406
Published: 2006
Other books in this series
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Thirty-one peer-reviewed papers provide the latest international research on the radiation effects on materials. Topics cover:
• Austenitic stainless steels
• Ferritic-martensitic stainless steels
• Embrittlement of pressure vessel steels
• Radiation damage fundamentals
• Ceramics for application in Generation IV systems
• Other nuclear energy system materials
Table of Contents
Behavior of Irradiated Type 316 Stainless Steels under Low- Strain-Rate Tensile Conditions
Akasaka N., Allen T., Cole J., Nakamura Y., Tsai H., Yamagata I., Yoshitake T.
Radiation-Induced Stress Relaxation of Welded Type 304 Stainless Steel Evaluated by Neutron Diffraction
Anzai H., Asano K., Ishiyama Y., Nakata K., Obata M., Root J., Sakamoto H.
Low Strain-Rate Microstructural Deformation Behavior in 316 Stainless Steel Irradiated in EBR-II
Akasaka N., Allen T., Cole J., Nakamura Y., Tsai H., Yamagata I., Yoshitake T.
Neutron Flux Effect on the Irradiation Hardening of Type 304 Stainless Steel
Asano K., Kodama M., Kumagai K., Nakamura T., Tanaka S., Torimaru T.
Modeling the Effects of Oversize Solute Additions on Radiation-Induced Segregation in Austenitic Stainless Steels
Hackett M., Simonen E., Was G.
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
Averty X., Bertin J., Bougault A., Brachet J., de Carlan Y., Rabouille O., Rozenblum F.
The Role of Grain Boundary Engineering on the High Temperature Creep of Ferritic-Martensitic Alloy T91
Gupta G., Was G.
Extrapolation of Fracture Toughness Data for HT9 Irradiated at 360–390°C
Gelles D., Kurtz R.
Development of Fuel Clad Materials for High Burn-up Operation of LWR
Cho H., Fujiwara M., Kimura A., Ukai S.
Small Angle Neutron Scattering Study of Irradiated Martensitic Steels: Relation Between Microstructural Evolution and Hardening
Alamo A., Averty X., de Carlan Y., de Novion C., Mathon M.
Radiation Resistance of Advanced Ferritic-Martensitic Steel HCM12A
Allen T., Gan J., Gupta G., Shutthanandan S., Tan L., Thevuthasan S., Tucker J., Was G.
Microstructural and Mechanical Characterization of Radiation Effects in Model Reactor Pressure Vessel Steels
Böhmert J., Ulbricht A., Viehrig H.
Effects of Neutron Irradiation on Precipitation in Reactor Pressure Vessel Steels
Ellis D., Faulkner R., Lu Z., Williams T.
Radiation- and Thermally-Induced Phosphorus Inter-Granular Segregation in Pressure Vessel Steels
Faulkner R., Flewitt P., Jones R., Lu Z.
Fracture Toughness, Thermo-Electric Power, and Atom Probe Investigations of JRQ Steel in I, IA, IAR, and IARA Conditions
Kalkhof R., Miller M., Nanstad R., Niffenegger M., Sokolov M., Tipping P.
Assessment of Neutron Irradiation-Induced Grain Boundary Embrittlement by Phosphorous Segregation in a Reactor Pressure Vessel Steel
Fujii K., Fukuya K., Kasada R., Kimura A., Nakata H., Shibata M.
Effects of Neutron Dose, Dose Rate, and Irradiation Temperature on the Irradiation Embrittlement of a Low-Copper Reactor Pressure Vessel Steel
Kasada R., Kimura A., Kudo T., Matsui H., Narui M.
Mechanical Property Changes in Reactor Vessel Materials Thermally Aged for 209000 H at 282 °C
Gunawardane H., Hall B., Rosinski S.
Recent Surveillance Data and a Revised Embrittlement Correlation
English C., Lott R., Rosinski S., Server W.
Use of Broken Charpy V-notch Specimens from a Surveillance Program for Fracture Toughness Determination
Chaouadi R., Gérard R., Lucon E., Scibetta M., van Walle E.
Dynamic Finite Element Modeling of Fracture in Charpy V-Notch Specimens of Weld Material 72W
Kumar A., McCoy J.
Effects of Proton Irradiation on Reactor Pressure Vessel Steel and Its Model Alloys
Hasegawa M., Kimura A., Matsui H., Shibamoto H., Yamaguchi S.
Correlated Formation and Stability of SIA Loops and Stacking Fault Tetrahedra in High Energy Displacement Cascades in Copper
Bacon D., Osetsky Y., Voskoboinikov R.
Atomic-Scale Simulation of Defect Cluster Formation in High-Energy Displacement Cascades in Zirconium
Bacon D., Osetsky Y., Voskoboinikov R.
Flow Localization Processes in Austenitic Alloys
Li M., Pan X., Stubbins J., Wu X.
Deformation Mechanism Maps of Unirradiated and Irradiated V-4Cr-4Ti
Li M., Zinkle S.
Plutonium-238 Alpha-Decay Damage Study of A Glass-Bonded Sodalite Ceramic Waste Form
Barber T., DiSanto T., Frank S., Giglio J., Goff K., Johnson S., Jue J., Noy M., O'Holleran T.
Microstructure Evolution in ZrC Irradiated with Kr ions
Allen T., Birtcher R., Gan J., Meyer M.
Mechanical Properties of Cubic Silicon Carbide after Neutron Irradiation at Elevated Temperatures
Katoh Y., Snead L.
Creep-Fatigue Behavior in High Strength Copper Alloys
Li M., Stubbins J.
Tensile, Flexural, and Shear Properties of Neutron Irradiated SiC/SiC Composites with Different Fiber-Matrix Interfaces
Hinoki T., Katoh Y., Kohyama A., Kondo S., Nozawa T., Ozawa K., Snead L.
Author Index
Committee: E10
Paper ID: STP1475-EB
DOI: 10.1520/STP1475-EB
ISBN-EB: 978-0-8031-5518-3
 ASTM International is a member of CrossRef.
0-8031-3401-0
978-0-8031-3401-0
STP1475-EB
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