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


    Effects of Radiation on Materials: 23rd International Symposium

    Lott Randy, Busby Jeremy
    Published: 2008

      Format Pages Price  
    PDF (11M) $74   ADD TO CART
    Hardcopy (shipping and handling) $74   ADD TO CART
    Hardcopy + PDF Bundle - Save 25%
    (shipping and handling)
    $111.00   ADD TO CART

    Cite this document

    X Add email address send
      .RIS For RefWorks, EndNote, ProCite, Reference Manager, Zoteo, and many others.   .DOCX For Microsoft Word

    Eighteen peer-reviewed papers focus on the irradiation embrittlement of reactor pressure vessel steels. This new publication provides a broad perspective on the development and application of trend curves used to predict fracture toughness transition temperatures in irradiated reactor pressure vessel steels. Papers cover materials ranging from erbium-tritide films to oxide dispersion strengthened (ODS) ferritic steels.

    Table of Contents

    Master Integrated Reactor Vessel Surveillance Program

    The Feasibility of Using a Risk-informed Approach for Calculating Reactor Pressure Vessel Heatup and Cooldown Operating Curves

    Monitoring of Radiation Embrittlement of the First and Second Generation of VVER RPV Steels

    Analysis of the Ductile-to-Brittle Transition Temperature Shift in a Commercial Power Plant With High Nickel Containing Weld Material

    Radiation Embrittlement of Cr-Ni-Mo and Cr-Mo RPV Steels

    Attenuation of Neutron Radiation Damage Through a Simulated RPV Wall

    Phosphorus Segregation and Intergranular Embrittlement in Thermally Aged and Neutron Irradiated Reactor Pressure Vessel Steels

    Information Fusion Embrittlement Models for U.S. Power Reactor Pressure Vessel Steels

    Strain Hardening During Mechanical Twinning and Dislocation Channeling in Irradiated 316 Stainless Steels

    Notch Strengthening and Its Impact on the Deformation and Fracture of 316L Stainless Steel

    Irradiation Hardening and Microstructure Evolution of Ion-irradiated ODS Ferritic Steels

    Modelling of Radiation Damage in Fe-Cr Alloys

    Kinetics of the Migration and Clustering of Extrinsic Gas in bcc Metals

    Modeling the Interaction of Helium with Dislocations and Grain Boundaries in Alpha-Iron

    DD Simulations of Dislocation-Crack Interaction During Fatigue

    Grain Growth in Nanocrystalline Metal Thin Films under In Situ Ion-Beam Irradiation

    Microstructural Features in Aged Erbium Tritide Films

    Internal Probe to Detect Defects from Cascades—In-situ Ion Irradiation Experiments Revisited

    Committee: E10

    DOI: 10.1520/STP1492-EB

    ISBN-EB: 978-0-8031-6826-8

    ISBN-13: 978-0-8031-3421-8