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    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


    Radiation Stability of WWER-440 Vessel Materials

    Management of Neutron Radiation Embrittlement: A View from the United States

    Radiation Embrittlement of Spanish Nuclear Reactor Pressure Vessel Steels

    Analysis of the Surveillance Results at Paks Nuclear Power Plant

    Surveillance of WWER-440Č Reactor Pressure Vessels

    Surveillance Data on Neutron Embrittlement of Modern Low-Sensitivity Steel

    A Utility Perspective on Management of Reactor Pressure Vessel Embrittlement

    Utilization of Reactor Pressure Vessel Surveillance Data in Support of Aging Management

    An Overview of Radiation Embrittlement Modeling for Reactor Vessel Steels

    B&W Owners Group Master Integrated Reactor Vessel Surveillance Program

    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

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

    Analysis of the Results from the Surveillance Specimen Program for Reactor Pressure Vessels of Nuclear Power Plant W-2 in Jaslovské Bohunice

    Fracture Properties of Irradiated A533B,Cl.1, A508,Cl.3, and 15Ch2NMFAA Reactor Pressure Vessel Steel

    Radiation Embrittlement and Annealing Recovery of CrNiMoV Pressure Vessel Steels with Different Copper and Phosphorus Content

    Investigation on the Impact Strength and Toughness of A533 Grade B Composition Weld Metal Using Small Specimens

    Influence of Specimen Orientation on the Upper Shelf Energy and Transition Temperature Shift of Reactor Pressure Vessel Steel Base Metal

    Mechanical and Nondestructive Testing of Irradiated Half Charpy Specimens

    Radiation Embrittlement of Soviet 1000-MW Pressurized Water Reactor Vessel Steel 15KH2NMFAA

    Radiation Effects on the Mechanical Properties of SA 508 Cl.3 Forging

    Irradiation Response of the IAEA CRP-3 Material FFA Measured by Fracture Toughness Specimens

    Analysis of Radiation Embrittlement Results from a French Forging Examined in the Second Phase of an IAEA-Coordinated Research Program

    Interactions of Defects with Dislocations in Reactor Pressure Vessel Steels

    Influence of Phosphorus on Thermal and Neutron Embrittlement of Pressure Vessel Steels

    Influence of Neutron Irradiation on the Microstructure and Mechanical Properties of 15Kh2MFA Steel

    Neutron Fluence Management to Optimize Pressure Vessel Lifetime

    Evaluation of the Recovery Annealing of the Reactor Pressure Vessel of NPP Nord (Greifswald) Units 1 and 2 by Means of Subsize Impact Specimens

    Irradiation and Annealing Behavior of 15Kh2MFA Reactor Pressure Vessel Steel

    Recovery of the Transition Temperature of Irradiated WWER-440 Vessel Metal by Annealing

    Thermal Annealing of the Reactor Pressure Vessel NPP Unit 2 in Jaslovské Bohunice for Its Radiation Embrittlement Regeneration

    Sensitivity Analysis of Thermal and Stress Fields in the Core Belt of a Pressurized Water Reactor

    Committee: E10

    DOI: 10.1520/STP1170-EB

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

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