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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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Table of Contents

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Behavior of Irradiated Type 316 Stainless Steels under Low- Strain-Rate Tensile Conditions
Yoshitake T., Yamagata I., Akasaka N., Nakamura Y., Tsai H., Cole J., Allen T.

Radiation-Induced Stress Relaxation of Welded Type 304 Stainless Steel Evaluated by Neutron Diffraction
Obata M., Root J., Ishiyama Y., Nakata K., Sakamoto H., Anzai H., Asano K.

Low Strain-Rate Microstructural Deformation Behavior in 316 Stainless Steel Irradiated in EBR-II
Cole J., Allen T., Tsai H., Yoshitake T., Yamagata I., Akasaka N., Nakamura Y.

Neutron Flux Effect on the Irradiation Hardening of Type 304 Stainless Steel
Torimaru T., Kodama M., Tanaka S., Nakamura T., Asano K., Kumagai K.

Modeling the Effects of Oversize Solute Additions on Radiation-Induced Segregation in Austenitic Stainless Steels
Hackett M., Was G., Simonen E.

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
de Carlan Y., Averty X., Brachet J., Bertin J., Rozenblum F., Rabouille O., Bougault A.

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., Kimura A., Ukai S., Fujiwara M.

Small Angle Neutron Scattering Study of Irradiated Martensitic Steels: Relation Between Microstructural Evolution and Hardening
Mathon M., de Carlan Y., Averty X., Alamo A., de Novion C.

Radiation Resistance of Advanced Ferritic-Martensitic Steel HCM12A
Allen T., Tan L., Tucker J., Gan J., Gupta G., Was G., Shutthanandan S., Thevuthasan S.

Microstructural and Mechanical Characterization of Radiation Effects in Model Reactor Pressure Vessel Steels
Ulbricht A., Böhmert J., Viehrig H.

Effects of Neutron Irradiation on Precipitation in Reactor Pressure Vessel Steels
Faulkner R., Lu Z., Ellis D., Williams T.

Radiation- and Thermally-Induced Phosphorus Inter-Granular Segregation in Pressure Vessel Steels
Lu Z., Faulkner R., Jones R., Flewitt P.

Fracture Toughness, Thermo-Electric Power, and Atom Probe Investigations of JRQ Steel in I, IA, IAR, and IARA Conditions
Nanstad R., Niffenegger M., Kalkhof R., Miller M., Sokolov M., Tipping P.

Assessment of Neutron Irradiation-Induced Grain Boundary Embrittlement by Phosphorous Segregation in a Reactor Pressure Vessel Steel
Kimura A., Shibata M., Kasada R., Fujii K., Fukuya K., Nakata H.

Effects of Neutron Dose, Dose Rate, and Irradiation Temperature on the Irradiation Embrittlement of a Low-Copper Reactor Pressure Vessel Steel
Kasada R., Kudo T., Kimura A., 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
Server W., Lott R., Rosinski S., English C.

Use of Broken Charpy V-notch Specimens from a Surveillance Program for Fracture Toughness Determination
Scibetta M., Lucon E., Chaouadi R., van Walle E., Gérard R.

Dynamic Finite Element Modeling of Fracture in Charpy V-Notch Specimens of Weld Material 72W
McCoy J., Kumar A.

Effects of Proton Irradiation on Reactor Pressure Vessel Steel and Its Model Alloys
Shibamoto H., Kimura A., Hasegawa M., Matsui H., Yamaguchi S.

Correlated Formation and Stability of SIA Loops and Stacking Fault Tetrahedra in High Energy Displacement Cascades in Copper
Voskoboinikov R., Osetsky Y., Bacon D.

Atomic-Scale Simulation of Defect Cluster Formation in High-Energy Displacement Cascades in Zirconium
Voskoboinikov R., Osetsky Y., Bacon D.

Flow Localization Processes in Austenitic Alloys
Wu X., Pan X., Li M., Stubbins J.

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
Frank S., DiSanto T., Goff K., Johnson S., Jue J., Barber T., Noy M., O'Holleran T., Giglio J.

Microstructure Evolution in ZrC Irradiated with Kr ions
Gan J., Meyer M., Birtcher R., Allen T.

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
Nozawa T., Ozawa K., Kondo S., Hinoki T., Katoh Y., Snead L., Kohyama A.

Author Index


Committee: E10
Paper ID: STP1475-EB
DOI: 10.1520/STP1475-EB
ISBN-EB: 978-0-8031-5518-3

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STP1475-EB