STP1513

    Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle: 24th Volume

    Busby Jeremy, Hanson Brady
    Published: 2010


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    Fifteen peer-reviewed papers examine radiation damage for the entire fuel cycle. Topics cover:
    • Surveillance programs around the world
    • Detailed characterization of irradiated microstructures
    • Radiation effects in oxide-dispersion strengthened alloys and austenitic stainless steels
    • Modeling helium bubbles
    • Finite-element modeling of fuel bundles
    • And much more!


    Table of Contents

    International Atomic Energy Agency Coordinated Research Projects on Structural Integrity of Reactor Pressure Vessels
    Nanstad R., Server W.

    Analysis of the Belgian Surveillance Fracture Toughness Database Using Conventional and Advanced Master Curve Approaches
    Gérard R., Lucon E., Scibetta M.

    Final Results from the Crack Initiation and Arrest of Irradiated Steel Materials Project on Fracture Mechanical Assessments of Pre-Irradiated RPV Steels Used in German PWR
    Gundermann A., Hein H., Keim E., Schnabel H., Seibert T.

    Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Materials
    Dohi K., Ishino S., Nishida K., Nomoto A., Soneda N.

    Magnox Steel Reactor Pressure Vessel Monitoring Schemes—An Overview
    Bolton C., Flewitt P., Moskovic R., Wootton M.

    Investigation of Beltline Welding Seam of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel
    Rindelhardt U., Schuhknecht J., Viehrig H., Weiss F.

    Microstructural Characterization of RPV Materials Irradiated to High Fluences at High Flux
    Dohi K., Matsuzawa H., Nishida K., Nomoto A., Soneda N., Tomimatsu M.

    Irradiation-Induced Grain-Boundary Solute Segregation and Its Effect on Ductile-to-Brittle Transition Temperature in Reactor Pressure Vessel Steels
    Iwase A., Matsuzawa H., Nishiyama Y., Onizawa K., Yamaguchi M.

    Irradiation-Induced Hardening and Embrittlement of High-Cr ODS Ferritic Steels
    Cho H., Kasada R., Kimura A., Lee J.

    Kinetic Monte Carlo Simulation of Helium-Bubble Evolution in ODS Steels
    Ghoniem N., Nagasawa K., Sharafat S., Takahashi A.

    Study of Microstructure and Property Changes in Irradiated SS316 Wrapper of Fast Breeder Test Reactor
    Anandaraj V., Karthik V., Kasi Viswanathan K., Muralidharan N., Parameswaran P., Raj B., Saroja S., Venkiteswaran C., Venugopal V., Vijayalakshmi M.

    Unusual Enhancement of Ductility Observed during Evolution of a “Deformation Wave” in 12Cr18Ni10Ti Stainless Steel Irradiated in BN-350
    Garner F., Gusev M., Maksimkin O., Osipov I., Silniagina N.

    Interrelationship between True Stress—True Strain Behavior and Deformation Microstructure in the Plastic Deformation of Neutron-Irradiated or Work-Hardened Austenitic Stainless Steel
    Kondo K., Miwa Y., Nishinoiri K., Tsukada T., Yamashita S.

    Influence of Neutron Irradiation on Energy Accumulation and Dissipation during Plastic Flow and Hardening of Metallic Polycrystals
    Garner F., Gusev M., Maksimkin O., Toktogulova D.

    Comparison of CANDU Fuel Bundle Finite Element Model with Unirradiated Mechanical Load Experiments
    Freire-Canosa J., Lampman T., Popescu A.

    Author Index

    Subject Index


    Committee: E10

    Paper ID: STP1513-EB

    DOI: 10.1520/STP1513-EB

    ISBN-EB: 978-0-8031-8417-6

    ISBN-13: 978-0-8031-3425-6

    ASTM International is a member of CrossRef.


    978-0-8031-3425-6
    STP1513-EB