STP1475

    Effects of Radiation on Materials: 22nd Symposium

    Allen TR, Lott RG, Busby JT, Kumar AS
    Published: 2006


      Format Pages Price  
    PDF (17M) $98   ADD TO CART
    Hardcopy (shipping and handling) $98   ADD TO CART
    Hardcopy + PDF Bundle - Save 25%
    (shipping and handling)
    $147.00   ADD TO CART


    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

    ISBN-13: 978-0-8031-3401-0

    ASTM International is a member of CrossRef.

    0-8031-3401-0
    978-0-8031-3401-0
    STP1475-EB