STP955: Evaluation of Ferritic Alloy Fe-2¼Cr-1Mo After Neutron Irradiation: Microstructural Development

    Gelles, DS
    Principal engineer, Westinghouse Hanford Co., Richland, WA

    Pacific Northwestern Laboratory, Richland, WA

    Pages: 28    Published: Jan 1987


    Abstract

    As part of a program to provide a data base on the bainitic alloy Fe-2¼Cr-1Mo for fusion energy applications, microstructural examinations are reported for nine specimen conditions for 2¼Cr-1Mo steel that had been irradiated by fast neutrons over the temperature range 390 to 510°C. Void swelling is found following irradiation at 400 to 480°C. Concurrently dislocation structure and precipitation developed. Peak void swelling, void density, dislocation density, and precipitate number density formed at the lowest temperature, approximately 400°C, whereas mean void size and mean precipitate size increased with increasing irradiation temperature. The examination results are used to provide interpretation of in-reactor creep, density change, and post irradiation tensile behavior.

    Keywords:

    neutron irradiation, alloys, swelling, ferritic alloys


    Paper ID: STP33844S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP33844S


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