Volume 3, Issue 3 (March 2006)

    Spent Fuel Monitoring with Silicon Carbide Semiconductor Neutron/Gamma Detectors

    (Received 20 June 2005; accepted 29 September 2005)

    Published Online: 2005

    CODEN: JAIOAD

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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 spent-fuel 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.


    Author Information:

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

    Doi, H
    Nuclear Development Corporation, Tokaimura Ibaraki,

    Ruddy, FH
    Westinghouse Electric Company, Pittsburgh, PA

    Seidel, JG
    Westinghouse Electric Company, Pittsburgh, PA

    Dulloo, AR
    Westinghouse Electric Company, Pittsburgh, PA


    Stock #: JAI13430

    ISSN: 1546-962X

    DOI: 10.1520/JAI13430

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    Author
    Title Spent Fuel Monitoring with Silicon Carbide Semiconductor Neutron/Gamma Detectors
    Symposium Reactor Dosimetry, 12th Volume, 2005-05-13
    Committee E10