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


    In-Reactor Creep of Selected Ferritic Alloys

    Published: 0

      Format Pages Price  
    PDF (196K) 12 $25   ADD TO CART
    Complete Source PDF (10M) 531 $165   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


    In-reactor creep data to a peak fluence of 5.7 × 1022 neutrons (n)/cm2 (E > 0.1 MeV) for irradiation temperatures between 380 and 570°C have been obtained for the ferritic alloys HT9, 9Cr-1Mo, and 2¼Cr 1Mo. Also, in-reactor creep data for HT9 has been obtained at 650°C at a fluence of 2.9 × 1022 n/cm2 (E > 0.1 MeV). For irradiation temperatures less than 520°C, the creep strains for all ferritic alloys are small and less than predicted for 20% cold-worked Type 316 stainless steel. At 570°C, thermal creep mechanisms become important and 2¼Cr-1Mo loses its creep resistance. HT9 loses its creep resistance at 650°C and exhibits large diametral strains (>24%).


    in-reactor creep, ferritic alloys, irradiation-induced creep, radiation

    Author Information:

    Puigh, RJ
    Senior scientist, Westinghouse Hanford Company, Richland, WA

    Committee/Subcommittee: E10.02

    DOI: 10.1520/STP37349S