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    Application of Ex-Vessel Neutron Dosimetry for Determination of Vessel Fluence

    Published: Jan 1989

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    Routine reactor cavity dosimetry measurements in four plants have been completed. Each of these measurements has included several multiple reaction sets that contain radiometric monitors and solid-state track recorders (SSTRs). The SSTRs are used to accurately determine fission rates using only extremely small amounts of very high purity fissionable material. The multiple reaction dosimetry sets were contained in holders suspended by wires extending from the top to the bottom of the cavity. These stainless steel wires were also analyzed to provide both fast and thermal neutron axial gradient data.

    A detailed discrete ordinates transport theory calculation was performed for each plant. These calculations included the cycle average neutron source distribution in the fuel and a detailed model of the cavity region. The calculations in general reproduce the measured gradient shapes but exhibit a consistent absolute bias. Although part of this bias probably arises from known cross-section deficiencies, some of the bias is estimated to arise from other, unknown, sources. Because of the general consistent bias of the measurements, a simple renormalization of the calculation allows the neutron flux to be evaluated at all points in the reactor vessel.


    reactor, vessel, neutron dosimetry, fluence

    Author Information:

    Lippincott, EP
    Westinghouse Electric Corporation, Pittsburgh, PA

    Anderson, SL
    Westinghouse Electric Corporation, Pittsburgh, PA

    Fero, AH
    Westinghouse Electric Corporation, Pittsburgh, PA

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP10071S