STP1170

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

    Steele LE
    Published: 1993


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    31 peer-reviewed papers cover:

    • National Perspectives

    • Surveillance Programs and Their Results

    • Fracture Approaches

    • Applied Research

    • Fundamental Research

    • Amelioration of Effects.


    Table of Contents

    Overview
    Steele L.

    Radiation Stability of WWER-440 Vessel Materials
    Amayev A., Kryukov A., Levit V., Sokolov M.

    Management of Neutron Radiation Embrittlement: A View from the United States
    Griesbach T., Server W.

    Radiation Embrittlement of Spanish Nuclear Reactor Pressure Vessel Steels
    Ballesteros A., Bros J., López A.

    Analysis of the Surveillance Results at Paks Nuclear Power Plant
    Oszvald F., Trampus P.

    Surveillance of WWER-440Č Reactor Pressure Vessels
    áš Páv T., Brumovský M.

    Surveillance Data on Neutron Embrittlement of Modern Low-Sensitivity Steel
    Glumac B., Loose A., Najžer M., Remec I., Trandafir A.

    A Utility Perspective on Management of Reactor Pressure Vessel Embrittlement
    Perrin J.

    Utilization of Reactor Pressure Vessel Surveillance Data in Support of Aging Management
    Mager T.

    An Overview of Radiation Embrittlement Modeling for Reactor Vessel Steels
    Griesbach T., Pavinich W., Server W.

    B&W Owners Group Master Integrated Reactor Vessel Surveillance Program
    Fyfitch S., Gross L., Lowe A., Moore K., Yoon K.

    Study by Positron Annihilation of Neutron Damage in a Pressurized Water Reactor (PWR) Pressure Vessel Steel After a 13-Year Irradiation in the CHOOZ A Reactor Surveillance Program
    Bourgoin J., Janot C., Moser P., Van Duysen J.

    Surveillance Dosimetry of the French 900-MW Pressurized Water Reactors (PWRs): Results, Uncertainties, and Reactor Series Effects
    Lloret R.

    Analysis of the Results from the Surveillance Specimen Program for Reactor Pressure Vessels of Nuclear Power Plant W-2 in Jaslovské Bohunice
    Beňo P., Kupča &.

    Fracture Properties of Irradiated A533B,Cl.1, A508,Cl.3, and 15Ch2NMFAA Reactor Pressure Vessel Steel
    Brumovský M., Havel R., Vacek M.

    Radiation Embrittlement and Annealing Recovery of CrNiMoV Pressure Vessel Steels with Different Copper and Phosphorus Content
    Havel R., Novosad P., Vacek M.

    Investigation on the Impact Strength and Toughness of A533 Grade B Composition Weld Metal Using Small Specimens
    Liu Q., Varga T.

    Influence of Specimen Orientation on the Upper Shelf Energy and Transition Temperature Shift of Reactor Pressure Vessel Steel Base Metal
    Hofmann G., Klausnitzer E., Leitz C.

    Mechanical and Nondestructive Testing of Irradiated Half Charpy Specimens
    Gillemot F., Oszwald F., Pozsgay G.

    Radiation Embrittlement of Soviet 1000-MW Pressurized Water Reactor Vessel Steel 15KH2NMFAA
    Shamardin V., Tulyakov G., Vishkarev O., Zvezdin Y.

    Radiation Effects on the Mechanical Properties of SA 508 Cl.3 Forging
    Marschall C., Milella P., Pini A.

    Irradiation Response of the IAEA CRP-3 Material FFA Measured by Fracture Toughness Specimens
    Ahlstrand R., Törrönen K., Valo M., Wallin K.

    Analysis of Radiation Embrittlement Results from a French Forging Examined in the Second Phase of an IAEA-Coordinated Research Program
    Bethmont M., Bocquet P., Houssin B., Soulat P.

    Interactions of Defects with Dislocations in Reactor Pressure Vessel Steels
    Mercier O., Munier A., Schaller R., Waeber W.

    Influence of Phosphorus on Thermal and Neutron Embrittlement of Pressure Vessel Steels
    Horowitz H., Miannay D., Soulat P.

    Influence of Neutron Irradiation on the Microstructure and Mechanical Properties of 15Kh2MFA Steel
    Keilová E., Kočík J., Páv T.

    Neutron Fluence Management to Optimize Pressure Vessel Lifetime
    Lefebvre J., Leroy P., Lloret R., Nimal J., Rieg C., Schaeffer H.

    Evaluation of the Recovery Annealing of the Reactor Pressure Vessel of NPP Nord (Greifswald) Units 1 and 2 by Means of Subsize Impact Specimens
    Ahlstrand R., Klausnitzer E., Lange D., Leitz C., Pastor D., Valo M.

    Irradiation and Annealing Behavior of 15Kh2MFA Reactor Pressure Vessel Steel
    Bergmann U., Bergner F., Hampe E., Leonhardt W., Popp K., Schützler H., Viehrig H.

    Recovery of the Transition Temperature of Irradiated WWER-440 Vessel Metal by Annealing
    Amayev A., Kryukov A., Sokolov M.

    Thermal Annealing of the Reactor Pressure Vessel NPP Unit 2 in Jaslovské Bohunice for Its Radiation Embrittlement Regeneration
    Čepček &., Kupča &.

    Sensitivity Analysis of Thermal and Stress Fields in the Core Belt of a Pressurized Water Reactor
    Glumac B., Najžer M.

    Author Index

    Subject Index


    Committee: E10

    Paper ID: STP1170-EB

    DOI: 10.1520/STP1170-EB

    ISBN-EB: 978-0-8031-5228-1

    ISBN-13: 978-0-8031-1478-4

    ASTM International is a member of CrossRef.

    0-8031-1478-8
    978-0-8031-1478-4
    STP1170-EB