STP1572

    Effects of Radiation on Nuclear Materials: 26th Volume

    Kirk Mark, Lucon Enrico
    Published: 2014


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    Featuring 10 symposium papers presented in Indianapolis, IN in June 2013. These papers have a rich history having evolved from five decades of tradition, from a symposium that has provided an international forum for the presentation of current research results, applications studies, and open discussion.

    Papers on radiation effects in reactor pressure vessel steels dominated The Effects of Radiation on Nuclear Materials symposium. More than half of the contributions to these papers are from international, expert authors.

    While a long-standing topic of research and practical interest to the nuclear engineering community, this topic retains its currency due the irreplaceability of the vessel and the critical role vessel safety calculations play in establishing the licensable life of the plant.


    Table of Contents

    Spectrum Effect Mitigation and Monitoring of the EPR Irradiation Surveillance Program
    Akamatsu M., Benhamou C., Churier-Bossennec H., Roch F., Todeschini P., Vaindirlis M.

    PWR Supplemental Surveillance Program
    Burgos B., Hall J., Hardin T., Server W.

    Surveillance Program Results for the High Flux Reactor Vessel Material
    Luzginova N., Nolles H., van den Berg F., van den Idsert P., van der Schaaf B.

    Microstructural Changes in Highly Irradiated 15Kh2MFA Steel
    Cammelli S., Gillemot F., Horváth &., Horváth M., Kovács A., Kresz N., Mayoral M., Oszwald F., Pareige P., Radiguet B., Török G., Ulbricht A.

    Microstructural Characterization of Irradiation-Induced MnNi-Rich Solute Cluster in Highly Neutron-Irradiated MnNiMo Alloyed Weld Metals
    Grovenor C., Hyde J., Lim J., Lozano-Perez S.

    Characterization of Precipitates in 316 Stainless Steel Neutron-Irradiated at ∼390°C by the Combination of CDF-TEM, EF-TEM, and HR-TEM
    Malaplate J., Pokor C., Renault-Laborne A., Tanguy B.

    Comparison of Charpy V-Notch-Energy-Based Embrittlement Trend Curves Developed in the United States
    Erickson M.

    Flux Effects on Radiation Induced Aging Behaviour of Low Alloy Steel Weld Material with High Nickel and Manganese Content
    Efsing P., Nilsson P., Roudén J.

    Final Results from the CARINA Project on Crack Initiation and Arrest of Irradiated German RPV Steels for Neutron Fluences in the Upper Bound
    Barthelmes J., Eiselt C., Ganswind J., Hein H., Keim E., Obermeier F., Schnabel H., Widera M.

    Empirical Analyses of Effects of the Heat Affected Zone and Post Weld Heat Treatment on Irradiation Embrittlement of Reactor Pressure Vessel Steel
    Erickson M., Troyer G.


    Committee: E10

    Paper ID: STP1572-EB

    DOI: 10.1520/STP1572-EB

    ISBN-EB: 978-0-8031-7590-7

    ISBN-13: 978-0-8031-7589-1

    ASTM International is a member of CrossRef.


    978-0-8031-7589-1
    STP1572-EB