STP1366

    The Effects of Flux on Radiation Embrittlement of Low-Copper Pressure Vessel Steels

    Published: Jan 2000


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    Abstract

    The effects of neutron flux (E>1MeV) on the radiation embrittlement of the low-copper RPV steels are investigated. Tested materials include the forging matrix (JF) weld (JW) of Japan's SA 508-3 steel as well as the matrix (CF) and weld (CW) of China's domestic RPV steel. JF and CF were irradiated to fluences from 3.2 to 4.9 × 1023n/m2(E>1MeV) at 280±5°C, JW and CW irradiated to fluences of 1.4 and 1.5 × 1023n/m2 at 290±5°C, respectively, in the test reactor. JF and JW are also used as surveillance specimens for PWR RPV, and two sets of surveillance data have been acquired. The experimental results indicate that the transition temperature shifts (ΔRTNDT) for JF irradiated in the test reactor are larger than those from surveillance specimens, when these ΔRTNDT are normalized to an effective fluence of 2×1023n/m2 (E>1MeV) and an effective temperature of 290°C. This shows notably the influence of neutron flux on ΔRTNDT. The mean ΔRTNDT for CF and CW is about 0.7 times that for JF and JW in terms of the normalized data, which imply the influences of the impurities besides Cu and microstructures on radiation embrittlement of low-copper RPV steels.

    Keywords:

    reactor pressure vessels, low-copper steels, irradiation, neutron flux, test reactor, surveillance, effective fluence, Charpy V-norch impact, transition temperature shift, matrix defects


    Author Information:

    Xu, Y
    Professor and Engineers, Nuclear Materials Laboratory, China Institute of Atomic Energy,

    Jia, X
    Professor and Engineers, Nuclear Materials Laboratory, China Institute of Atomic Energy,

    Zhang, C
    Professor and Engineers, Nuclear Materials Laboratory, China Institute of Atomic Energy,

    Ning, G
    Professor and Engineers, Nuclear Materials Laboratory, China Institute of Atomic Energy,

    Yu, Q
    Graduate student, China Nuclear Industry Graduate School,


    Paper ID: STP12386S

    Committee/Subcommittee: E10.01

    DOI: 10.1520/STP12386S


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