STP1295: Development of New Zirconium Alloys for a BWR

    Etoh, Y
    Researcher and senior researcher, Nippon Nuclear Fuel Development Co., Ltd., Ibaraki-ken,

    Shimada, S
    Researcher and senior researcher, Nippon Nuclear Fuel Development Co., Ltd., Ibaraki-ken,

    Yasuda, T
    Senior engineer, Hitachi Ltd., Ibaraki-ken,

    Ikeda, T
    Senior specialist, Toshiba Corp., Kanagawa-ken,

    Adamson, RB
    Manager and senior engineer, GE Nuclear Energy, Pleasanton, CA

    Chen, J-SF
    Manager and senior engineer, GE Nuclear Energy, Pleasanton, CA

    Ishii, Y
    Staff researcher and researcher, Tokyo Electric Power Co., Kanagawa-ken,

    Takei, K
    Staff researcher and researcher, Tokyo Electric Power Co., Kanagawa-ken,

    Pages: 25    Published: Jan 1996


    Abstract

    Specimens for irradiation testing in a commercial BWR were prepared from 24 kinds of Zr alloys. The corrosion performance of these specimens was investigated after irradiation for up to four cycles. Two cycles of irradiation were not always sufficient to identify the lowest corrosion alloys. Marked acceleration of corrosion occurred for many alloys between one and four cycles. The onset of mildly accelerated oxidation was observed for standard Zircaloy-2 at four cycles of irradiation. On the other hand, for Zircaloy-like alloys, increasing Fe and Ni contents or decreasing the Sn content promoted a saturation oxidation between two and four cycles of irradiation. The effects of alloying elements on corrosion behavior were evaluated by both in-pile and out-of-pile corrosion tests. The alloying elements Fe, Cr, and Ni, which have smaller valences than Zr, improved the in-pile corrosion resistance of Zr alloys, while the alloying elements Nb, Mo, and Te, which have larger valences than Zr, were responsible for increased weight gain during the irradiation test in the BWR.

    Keywords:

    Zr alloys, BWR, corrosion, accelerated corrosion, valence, nodular corrosion, hydrogen pickup, high burnup


    Paper ID: STP16203S

    Committee/Subcommittee: B10.01

    DOI: 10.1520/STP16203S


    CrossRef ASTM International is a member of CrossRef.