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Effects of Radiation on Materials: 22nd Symposium Allen TR Pages: 406       Published: 2006

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Table of Contents

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 JH, 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 JI, Allen TR, 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 MJ, Was GS, Simonen EP

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-C, 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 GS

Extrapolation of Fracture Toughness Data for HT9 Irradiated at 360390°C
Gelles DS, Kurtz RJ

Development of Fuel Clad Materials for High Burn-up Operation of LWR
Cho HS, Kimura A, Ukai S, Fujiwara M

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

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

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

Effects of Neutron Irradiation on Precipitation in Reactor Pressure Vessel Steels
Faulkner RG, Lu Z, Ellis D, Williams TJ

Radiation- and Thermally-Induced Phosphorus Inter-Granular Segregation in Pressure Vessel Steels
Lu Z, Faulkner RG, Jones RB, Flewitt PEJ

Fracture Toughness, Thermo-Electric Power, and Atom Probe Investigations of JRQ Steel in I, IA, IAR, and IARA Conditions
Nanstad RK, Niffenegger M, Kalkhof RD, Miller MK, Sokolov MA, Tipping Ph

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 HP, Hall BJ, Rosinski ST

Recent Surveillance Data and a Revised Embrittlement Correlation
Server WL, Lott RG, Rosinski ST, English CA

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 JH, Kumar AS

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 RE, Osetsky YN, Bacon DJ

Atomic-Scale Simulation of Defect Cluster Formation in High-Energy Displacement Cascades in Zirconium
Voskoboinikov RE, Osetsky YN, Bacon DJ

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

Deformation Mechanism Maps of Unirradiated and Irradiated V-4Cr-4Ti
Li M, Zinkle SJ

Plutonium-238 Alpha-Decay Damage Study of A Glass-Bonded Sodalite Ceramic Waste Form
Frank SM, DiSanto T, Goff KM, Johnson SG, Jue JF, Barber TL, Noy M, O'Holleran TP, Giglio JJ

Microstructure Evolution in ZrC Irradiated with Kr ions
Gan J, Meyer MK, Birtcher RC, Allen TR

Mechanical Properties of Cubic Silicon Carbide after Neutron Irradiation at Elevated Temperatures
Katoh Y, Snead LL

Creep-Fatigue Behavior in High Strength Copper Alloys
Li M, Stubbins JF

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 LL, Kohyama A

Author Index


Committee: E10
Paper ID: STP1475-EB
DOI: 10.1520/STP1475-EB

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STP1475-EB