STP1490

    Spent Fuel Monitoring with Silicon Carbide Semiconductor Neutron/Gamma Detectors

    Published: Jan 2007


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    Abstract

    Silicon carbide semiconductor radiation detectors have been demonstrated for neutron and gamma-ray monitoring of spent nuclear fuel. Neutrons and gamma rays were monitored simultaneously over a 2050-h period, resulting in a gamma dose of over 6000 Gy to the SiC detector. No changes in the neutron and gamma-ray sensitivity were observed as a result of the gamma-ray exposure. After the spentfuel measurements, the absolute neutron sensitivity was determined in a standard neutron field, and the degree of gamma-ray and neutron spectrum overlap were determined through exposures in intense gamma ray fields. No overlap was observed for gamma-ray dose rates up to 100 G/h.

    Keywords:

    silicon carbide, detectors, semiconductor, spent fuel, neutrons, gamma rays, burnup


    Author Information:

    Natsume, T.
    Mitsubishi Heavy Industries, LTD., Hyogo-ken,

    Doi, H.
    Nuclear Development Corporation 622-12, Tokaimura Ibaraki,

    Ruddy, F. H.
    Westinghouse Electric Company, Pittsburgh, PA

    Seidel, J. G.
    Westinghouse Electric Company, Pittsburgh, PA

    Dulloo, A. R.
    Westinghouse Electric Company, Pittsburgh, PA


    Paper ID: STP45471S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP45471S


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