STP909

    Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Second Volume)

    Steele LE
    Published: 1986


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    STP 909 has sixteen peer-reviewed papers divided into four sections that reflect changes in the nuclear power industry occurring since 1981, including escalating capital requirements and a growing worldwide dependence on nuclear power for electricity production. The four sections of this book are:

    • Overview of National Programs
    • Surveillance and Other Radiation Embrittlement Studies
    • Pressure Vessel Integrity and Regulatory Considerations
    • and Mechanisms of Irradiation Embrittlement.


    Table of Contents

    Introduction
    Steele L.

    Overview of Studies in the United Kingdom on Neutron Irradiation Embrittlement of Pressure Vessel Steels
    Davies L., Ingham T.

    Summary
    Steele L.

    Irradiation Effects in Reactor Pressure Vessel Steels: A Nuclear Regulatory Commission Perspective
    Randall P., Serpan C.

    Irradiation Behavior of Reactor Pressure Vessel Steels from the Research Program on the Integrity of Components
    Ahlf J., Bellmann D., Föhl J., Hebenbrock H., Schmitt F., Spalthoff W.

    Surveillance Programs and Irradiation Embrittlement Research of the Loviisa Nuclear Power Plant
    Ahlstrand R., Bärs B., Törrönen K., Valo M.

    Effect of Irradiation on the Elasto-Plastic Toughness of Pressure Vessel Steels
    Mundheri M., Petrequin P., Soulat P.

    Prediction of Reference Transition Temperature Increase Due to Neutron Irradiation Exposure
    Maricchiolo C., Milella P., Pini A.

    Boiling Water Reactor (BWR) Pressure Vessel Surveillance Program
    Anantharaman S., Balakrishnan K., Chatterjee S., Roy P., Sivaramakrishnan K., Viswanathan U.

    Static Fracture Criteria Evaluation Using Small Specimens
    Gillemot F., Havas I., Szabó L.

    Investigations and Measures to Guarantee the Safety of a Pressurized Water Reactor's Pressure Vessel Against Brittle Fracture
    Kaun U., Koehring F.

    Basis for Revision 2 of the U. S. Nuclear Regulatory Commission's Regulatory Guide 1.99
    Randall P.

    Reactor Pressure Vessel Structural Implications of Embrittlement to the Pressurized-Thermal-Shock Scenario
    Föhl J., Iskander S., Sauter A.

    Safety Standard KTA 3203: Monitoring Radiation Embrittlement of Reactor Pressure Vessels of Light-Water Reactors
    Ernst K., Klausnitzer E., Leitz C.

    Microanalytical Studies of Pressure Vessel Weld Materials
    English C.

    Irradiation Embrittlement of Reactor Pressure Vessel Steels: Mechanisms, Models, and Data Correlations
    Lucas G., Odette G.

    Annealing and Reirradiation Response of Irradiated Pressure Vessel Steels
    Lott R., Mager T., Shogan R., Yanichko S.

    Effect of Various Metallurgical Microstructures on the Response of the Nickel-Molybdenum-Chromium BH 70 Steel to Neutron Irradiation at 285°C
    Vacek M.

    Author Index

    Subject Index


    Committee: E10

    Paper ID: STP909-EB

    DOI: 10.1520/STP909-EB

    ISBN-EB: 978-0-8031-4975-5

    ISBN-13: 978-0-8031-0473-0

    ASTM International is a member of CrossRef.

    0-8031-0473-1
    978-0-8031-0473-0
    STP909-EB