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

    If you are an ASTM Compass Subscriber and this document is part of your subscription, you can access it for free at ASTM Compass
    STP1046

    Segregation to Surfaces in Irradiated Stainless Steels

    Published: 01 January 1990


      Format Pages Price  
    PDF (232K) 13 $25   ADD TO CART
    Complete Source PDF (18M) 672 $247   ADD TO CART

    Cite this document

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


    Abstract

    An irradiated 316 (UNS S31600) stainless steel (SS) alloy consistently showed phosphorus segregation to surfaces at temperatures in which thermal segregation is negligible. Phosphorus segregation did not occur in other irradiated 300 series alloys examined. The segregation model of Lam et al. was used to show that interstitial-solute binding and migration is a likely mechanism for the measured irradiation-induced phosphorus segregation. Surface segregation of sulfur was observed but the segregation mechanism was not established. Segregation of other impurities such as silicon and nitrogen or alloying elements such as chromium were not observed.

    Keywords:

    segregation, solute, stainless steel, irradiation-assisted stress corrosion cracking.


    Author Information:

    Simonen, EP
    Senior research scientist and senior staff scientist, Pacific Northwest Laboratory, Richland, WA

    Bradley, ER
    Product metallurgist, Sandvik Special Metals Corporation, Kennewick, WA

    Jones, RH
    Senior research scientist and senior staff scientist, Pacific Northwest Laboratory, Richland, WA


    Committee/Subcommittee: E10.03

    DOI: 10.1520/STP24657S