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    STP1547

    Effects of Radiation on Nuclear Materials: 25th Volume

    Yamamoto Takuya, Sokolov Mikhail, Hanson Brady
    Published: 2013


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    Seventeen peer-reviewed papers focus on the latest research on the effects of radiation on nuclear materials. These papers focus on:

    Light Water Reactor Sustainability Issues and Programs that address the multiple challenges of extended reactor life, including detailed coverage of irradiation embrittlement of reactor pressure vessel steels.

    Synergistic Effects of Gas Atoms (i.e. helium and hydrogen) and Displacement Damage, with an emphasis on the unprecedented challenge to structural and plasma-facing materials in nuclear fusion reactors.

    Sections cover:
    • Reactor Pressure Vessel Steels
    • Synergistic effects of Helium and displacement damage
    • Austenitic steels, Ni, Zr, and Al-Mg alloys, and Polyethylene
    • Modeling of Radiation Effects


    Table of Contents

    Long Term Irradiation Phenomena in RPV Steels—The LONGLIFE Project

    A Wide-Range Embrittlement Trend Curve for Western Reactor Pressure Vessel Steels

    Long Term Irradiation Effects on the Mechanical Properties of Reactor Pressure Vessel Steels from Two Commercial PWR Plants

    Fracture Mechanics Characterisation of Forged Base Metal Ring of the Decommissioned Reactor Pressure Vessel of NPP Greifswald WWER-440 Unit 4

    Microstructure Response of WWER-440 Reactor Pressure Vessel Weld Material After Irradiation and Annealing Treatment

    Approach of He/dpa Synergistic Effects in Iron-Based Materials Using JANNUS

    Modeling and TEM Investigation of Helium Bubble Growth in RAFM Steels Under Neutron Irradiation

    Use of MeV Ion Beams to Simulate the Irradiation Effects in Advanced Materials at JANNUS Saclay

    Embrittlement of Nickel Alloys in a CANDU Reactor Environment

    CANDU (CANadian Deuterium Uranium)® is a registered trademark or Atomic Energy of Canada Limited.


    Irradiation Testing of Zirconium Alloys and Stainless Steel in Fast Breeder Test Reactor, India

    Material Investigations on Highly Irradiated Aluminum Magnesium Alloys for Lifetime Assessment of a Neutron Beam Tube in the BER II Research Reactor

    (U)HMWPE as Neutron Radiation Shielding Materials: Impact of Gamma Radiation on Structure and Properties

    Atomistic Investigations of Intrinsic and Extrinsic Point Defects in bcc Uranium

    Impact of Vacancy-Type Defects on Thermal Conductivity of β-SiC: Molecular Dynamics Versus an Analytical Approach

    A Phenomenological Micromechanical Model of FCC Metals under Radiation Induced Crystal Defects

    Development of Models for Irradiation-induced Changes to Microstructure and Stress–Strain Relations of Austenitic Steels

    Cluster Dynamics Simulation on Microstructure Evolution of Austenitic Stainless Steel and α-Iron Under Cascade Damage Condition

    Dislocation Bias Calculations in Metals Using a Combined Finite-Element Rate-Theory Approach

    Author and Subject Index


    Committee: E10

    DOI: 10.1520/STP1547-EB

    ISBN-EB: 978-0-8031-7563-1

    ISBN-13: 978-0-8031-7533-4

    ASTM International is a member of CrossRef.


    978-0-8031-7533-4
    STP1547-EB