STP1366: Temperature-Shift of Void Swelling Observed in Annealed Fe-18Cr-10Ni-Ti Stainless Steel Irradiated in the Reflector Region of BOR-60

    Neustroev, VS
    Leading Research Scientist, Head of Laboratory, Senior Research Scientist, Senior Research Scientist, Research Institute of Atomic Reactors, Dimitrovgrad,

    Shamardin, VK
    Leading Research Scientist, Head of Laboratory, Senior Research Scientist, Senior Research Scientist, Research Institute of Atomic Reactors, Dimitrovgrad,

    Ostrovsky, ZE
    Leading Research Scientist, Head of Laboratory, Senior Research Scientist, Senior Research Scientist, Research Institute of Atomic Reactors, Dimitrovgrad,

    Pecherin, AM
    Leading Research Scientist, Head of Laboratory, Senior Research Scientist, Senior Research Scientist, Research Institute of Atomic Reactors, Dimitrovgrad,

    Garner, FA
    Senior Staff Scientist, Pacific Northwest National Laboratory, Richland, WA

    Pages: 9    Published: Jan 2000


    Abstract

    Evidence has been provided to support the “temperature-shift” concept of swelling. The swelling of annealed X18H10T stainless steel in the BOR-60 fast reactor at PWR-relevant dpa rates was found to be higher than predicted by a swelling equation developed from data obtained at dpa rates almost an order of magnitude higher. These data were derived from identical hexagonal wrappers irradiated in both in-core and reflector positions. Based on these results, irradiation in PWRs would yield higher swelling to lower temperatures than would occur in core regions of fast reactors.

    Keywords:

    stainless steels, swelling, pressurized water reactors, fast reactors


    Paper ID: STP12432S

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP12432S


    CrossRef ASTM International is a member of CrossRef.