STP955

    Development of Modified Type 316 Stainless Steel for Fast Breeder Reactor Fuel Cladding Tubes

    Published: Jan 1987


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    Abstract

    It is suggested from the understanding of the creep behavior in cold-worked austenitic stainless steels that high out-of-reactor creep strength correlates with superior inreactor swelling resistance. The additions of small amounts of boron, phosphorus, titanium, and niobium were found to be beneficial for the improvement of the creep strength of cold-worked Type 316 stainless steel. These additions caused finely dispersed precipitates in the grains during creep at elevated temperatures and resulted in retarding the recovery of the dislocation structures induced by cold working. The cold-worked modified Type 316 stainless steel having improved out-of-reactor creep strength showed excellent resistance to swelling. It is considered that higher stability of dislocation structures at elevated temperatures is also beneficial for the improvement of swelling resistance.

    Keywords:

    Type 316 stainless steel, creep strength, cold working, grain size, element composition, ion bombardment, neutron irradiation, swelling


    Author Information:

    Fujiwara, M
    Senior researcher, researcher, and general manager, Iron and Steel Technology Center, Kobe Steel, Ltd., Chuo-ku, Kobe,

    Uchida, H
    Senior researcher, researcher, and general manager, Iron and Steel Technology Center, Kobe Steel, Ltd., Chuo-ku, Kobe,

    Ohta, S
    Senior researcher, researcher, and general manager, Iron and Steel Technology Center, Kobe Steel, Ltd., Chuo-ku, Kobe,

    Yuhara, S
    General manager, deputy general manager, and assistant senior engineer, Power Reactor and Nuclear Fuel Development Corp., Oarai Engineering Center, Ibaraki-ken,

    Tani, S
    General manager, deputy general manager, and assistant senior engineer, Power Reactor and Nuclear Fuel Development Corp., Oarai Engineering Center, Ibaraki-ken,

    Sato, Y
    General manager, deputy general manager, and assistant senior engineer, Power Reactor and Nuclear Fuel Development Corp., Oarai Engineering Center, Ibaraki-ken,


    Paper ID: STP33813S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP33813S


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