You are being redirected because this document is part of your ASTM Compass® subscription.
    This document is part of your ASTM Compass® subscription.

    STP380

    Flow and Fracture of Metals and Alloys in Nuclear Environments

    Committee E10
    Published: 1965


      Format Pages Price  
    PDF (13M) $125   ADD TO CART
    Hardcopy (shipping and handling) $125   ADD TO CART
    Hardcopy + PDF Bundle - Save 25%
    (shipping and handling)
    $187.50   ADD TO CART



    Table of Contents

    Introduction

    Mechanisms of Radiation Damage in Reactor Materials

    Mechanisms of Radiation-Induced Mechanical Property Changes

    Irradiation Hardening and Embrittlement in Body-Centered Cubic Transition Metals

    Computer Studies of Neutron Irradiation and Annealing in Finite BCC Iron Specimens

    Effects of Irradiation in Iron and Steels

    Low-Temperature Embrittlement of Iron, Iron Alloys, and Steels by Neutron Irradiations

    Effect of Irradiation on Bend Transition Temperatures of Molybdenum- and Columbium-Base Alloys

    Irradiation Effects on High-Temperature Reactor Structural Metals

    Recovery of Defects in Neutron-Irradiated Tungsten

    The Nature and Annealing Behavior of Irradiation Damage in Molybdenum

    Effects of Irradiation in Austenitic Steels and Other High-Temperature Alloys

    The Flow and Fracture Properties of Unirradiated Stainless Steels

    The Combined Effects of Temperature and Irradiation on the Mechanical Properties of Austenitic Stainless Steels

    The Effect of Irradiation Temperature on the Post-Irradiation Stress-Strain Behavior of Stainless Steel

    In-Reactor Stress-Rupture Properties of a 20Cr-25Ni, Columbium-Stabilized Steel

    New Information on Neutron Embrittlement and Embrittlement Relief of Reactor Pressure Vessel Steels

    In-Depth Embrittlement of a Simulated Pressure Vessel Wall Of A302-B Steel

    Strain-Cycle Phenomena In Thin-Wall Tubing

    Effects of Irradiation on A302-B Steel Subjected to a Multiaxial Stress Distribution

    In-Reactor Studies of Low-Cycle Fatigue Properties of a Nuclear Pressure Vessel Steel

    Effects of Neutron Irradiation on the Flow and Fracture Behavior of Zircaloy-2

    In-Reactor Creep of Cold-Worked Zircaloy-2

    Gas Formation and Compression Fractures in Irradiated Beryllium

    The Use of Materials Properties by the Reactor Vessel Designer

    The Significance of Recent Developments in Fracture Mechanics In Great Britain In Relation To The Safety Of Reactor Pressure Vessels

    The Important Materials Parameters Affecting the Performance of Nuclear Reactor Pressure Vessels

    Crack Propagation Tests on Zircaloy-2 Reactor Pressure Tubing in Both the Normal and Hydrided Conditions

    Insurance Aspects of Radiation Damage in Reactor Structures


    Committee: E10

    DOI: 10.1520/STP380-EB

    ISBN-EB: 978-0-8031-6007-1

    ISBN-13: 978-0-8031-6161-0

    ASTM International is a member of CrossRef.

    0-8031-6161-1
    978-0-8031-6161-0
    STP380-EB