STP1001

    Power Reactor Neutron Dosimetry: Experimental Estimate of the Influences Due to Local Changes in Core Configuration and Gamma-Induced Reactions

    Published: Jan 1989


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    Abstract

    For the evaluation of neutron flux densities in reactor pressure vessel surveillance analyses a detailed knowledge of the local power history is required. In this paper a new method is proposed which reconstructs experimentally the effects of the local power history through the analysis of the measured activities in fission dosimeters. The validity of the method was tested by comparing measurements carried out at Caorso BWR plant with neutron flux density computations performed using the DOT 4.2 code.

    The same measurements and computations were utilized for carrying out an estimate of the gamma-ray flux density at the irradiation position.

    Keywords:

    BWR, neutron flux density, neutron energy spectra, dosimetry


    Author Information:

    Alloggio, G
    ENEL, Ente Nazionale per l'Energia Elettrica, Centro di Ricerca Termica e Nucleare (CRTN), Milan,

    Borioli, E
    ENEL, Ente Nazionale per l'Energia Elettrica, Centro di Ricerca Termica e Nucleare (CRTN), Milan,

    Brega, E
    ENEL, Ente Nazionale per l'Energia Elettrica, Centro di Ricerca Termica e Nucleare (CRTN), Milan,

    Sandrelli, G
    ENEL, Ente Nazionale per l'Energia Elettrica, Centro di Ricerca Termica e Nucleare (CRTN), Milan,

    Cesana, A
    Politecnico di Milano, Istituto di Ingegneria Nucleare, Centro Studi Nucleari E. Fermi (CESNEF), Milan,

    Terrani, M
    Politecnico di Milano, Istituto di Ingegneria Nucleare, Centro Studi Nucleari E. Fermi (CESNEF), Milan,


    Paper ID: STP10087S

    Committee/Subcommittee: E10.05

    DOI: 10.1520/STP10087S


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