STP1046V2

    Consideration of Calculated and Experimental Neutron Dosimetry for Out-of-Core Metallurgy Irradiation Experiments at the Buffalo Reactor

    Published: Jan 1990


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    Abstract

    Experimental neutron dosimetry measurements are compared to those derived from calculated neutron spectrum-averaged cross sections for the neutron fields associated with the University of Buffalo Reactor (UBR) where metallurgical specimens are irradiated for Materials Engineering Associates (MEA). The reaction rate measurements were conducted at the Idaho National Engineering Laboratory (INEL) and spectral index comparisons were carried out at the National Institute of Standards and Technology (NIST). The series of one- and two-dimensional DOT transport calculations were accomplished at the University of Stuttgart to determine spectrum-average cross sections for two out-of-core metallurgical irradiation test locations. The calculations address the issue of spectrum sensitivity to environmental changes near the metallurgical irradiation regions. Calculated spectral indices (ratios of cross sections) are observed to agree with measured reaction rate ratios. The impact of the variations and uncertainties of the dosimetry cross sections needed to derive exposure parameters for the metallurgy tests from in situ dosimetry is discussed.

    Keywords:

    neutron dosimetry, neutron spectrum calculations, neutron transport, test reactor irradiations


    Author Information:

    McGarry, Emmert D.
    Physicist, National Institute of Standards and Technology, Gaithersburg, MD

    Rogers, J.
    Idaho National Engineering Laboratory, Idaho Falls, ID

    Prillinger, G.
    University of Stuttgart, Stuttgart,

    Hawthorne, J. Russell
    Materials Engineering Associates, Lanham, MD


    Paper ID: STP49482S

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP49482S


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