STP457

    Irradiation Effects in Structural Alloys for Thermal and Fast Reactors

    Committee E-10 on Radioisotopes and Radiation Effects

    Pages: 435

    Published: 1969

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    Table of Contents

    Introduction

    The Effect of Cold Work, Thermal Treatment, and Neutron Irradiation on the Fracture Toughness of Zircaloy-2
    Hoagland R., Rowe R.

    Comparison of In-Reactor Creep and Postirradiation Creep Tests of Structural Materials for Nuclear Applications
    Gilbert E., Harding N.

    High-Temperature Tensile Properties of Unirradiated and Thermal Reactor Irradiated Nimonic PE16
    Broomfield G.

    Irradiation-Induced Embrittlement in Stainless Steel at Elevated Temperature
    Kangilaski M., Perrin J., Wullaert R.

    Irradiation Tests of Several Steels for Reactor Pressure Vessels
    Hasegawa M.

    Initial Assessments of Notch Ductility Behavior of A533 Pressure Vessel Steel with Neutron Irradiation
    Hawthorne J., Potapovs U.

    Notch Ductility, Tensile and Neutron Spectrum Analyses of PM-2A Reactor Pressure Vessel
    Serpan C., Watson H.

    Irradiation Effects in Pressure Vessel Materials for Steam-Cooled Fast Reactors
    Grounes M., Lindhagen P.

    The Effect of Substructure on the Biaxial Strength and Irradiation Stability of ASTM A 302 Grade B Steel
    Flynn P., Trozera T.

    Effects of Interstitial Elements on Radiation Hardening in Mild Steels
    Harries D., Little E.

    Radiation Hardening and Embrittlement in a Reactor Pressure Vessel Steel
    Berggreen R., Hinkle N., Stelzman W., Wechsler M.

    Development of Austenitic Stainless Steels with Improved Resistance to Elevated-Temperature Irradiation Embrittlement
    Bloom E., Weir J.

    Development of a Titanium-Modified Hastelloy N with Improved Resistance to Radiation Damage
    McCoy H., Weir J.

    Effects of Yttrium on the Structure and Post-Irradiation Tensile Properties of an Iron-Chromium-Aluminum Alloy
    Arkell D., Dewey M., Harries D., Hughes J., Roberts A.

    Development of Fuel Cladding for Fast Reactors
    Cunningham G.

    Effect of Irradiation on Mechanical Properties of Cobalt-Base Alloys
    Chow J.

    Neutron Dosimetry for Fast-Reactor Irradiation and Surveillance Testing
    McElroy W., Yoshikawa H.

    High-Temperature Embrittlement of AISI Type 316 Austenitic Stainless Steels after Irradiation
    Andre J., Erler J., Malkin J., Weisz M.

    Postirradiation Tensile Behavior of 300 Series Stainless Steels
    Holmes J., Lovell A., Robbins R.

    Multiaxial In-Reactor Stress-Rupture Strength of Stainless Steels and a Nickel Alloy
    Böhm H., Hauck H., Laue H.

    Comparison of Radiation Damage Studies and Fuel Cladding Performance for lncoloy-800
    Busboom H., Comprelli F., Spalaris C.

    Effects of Neutron Irradiation on Creep-Rupture Properties of Type 316 Stainless Steel Tubes
    Bell I., Glendinning A., Standring J., Tickle H.


    Committee: E10

    Paper ID: STP457-EB

    DOI: 10.1520/STP457-EB

    ISBN-EB: 978-0-8031-6036-1

    ISBN-PRINT: 978-0-8031-6190-0

    ASTM International is a member of CrossRef.

    0-8031-6190-5
    978-0-8031-6190-0
    STP457-EB