STP1047: An Assessment of Fe-Cr-Mn Austenitic Alloys for Fusion Service Using Fast Reactor Irradiation

    Garner, FA
    Staff scientist and research scientist, Pacific Northwest Laboratory, Richland, WA

    McCarthy, JM
    Staff scientist and research scientist, Pacific Northwest Laboratory, Richland, WA

    Pages: 11    Published: Jan 1990


    Abstract

    A series of model Fe-Cr-Mn alloys and various solute-modified high manganese alloys have been irradiated in the Fast Flux Test Facility in order to provide an early assessment of the consequences of substituting manganese for nickel in austenitic stainless steel. The purpose of this substitution is to reduce the level of long term radioactivation of this alloy, a candidate structural material for use in fusion energy devices.

    Simple Fe-Mn and Fe-Cr-Mn alloys were found to exhibit much of the same behavior observed in Fe-Ni and Fe-Ni-Cr alloys. In particular, they tend to swell at ∼1%/dpa after an incubation period that is dependent on irradiation temperature, alloy composition and cold working. The phase stability, both in and out of reactor, is altered substantially by the substitution of manganese, however. It nonetheless appears that appropriate levels of solute modification can be used to improve both the swelling resistance and phase stability. An alloy with a base composition of Fe-20Mn-15Cr appears to offer the best promise for further research.

    Keywords:

    neutron irradiation, Fe-Cr-Mn steels, Fe-Cr-Mn-Ni steels, void swelling, phase stability, fusion reactors


    Paper ID: STP24946S

    Committee/Subcommittee: E10.02

    DOI: 10.1520/STP24946S


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