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    STP1398

    BWR Neutron Fluence Computations using MF3D

    Published: 0


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    Abstract

    A full three dimensional model in a quadrant of an operating BWR has been modeled using MCNP to calculate flux spectrum and fluence levels at various locations in the reactor system. The model is being benchmarked against test data obtained over a complete fuel cycle of the host BWR. Preliminary comparisons of the calculated data to measured data are very encouraging.

    Keywords:

    BWR, fluence, flux spectra, neutron, gamma


    Author Information:

    Sitaraman, S
    Principal Engineer, GE Nuclear Energy, San Jose, CA

    Chiang, R-T
    Principal Engineer, GE Nuclear Energy, San Jose, CA

    Kruger, RM
    Principal Engineer, Schafer Corporation, Sunol, CA

    Jenkins, AL
    Project Manager, GE Nuclear Energy, San Jose, CA

    Asano, K
    Researcher, The Tokyo Electric Power Company, Yokohama,

    Koyabu, K
    Researcher, The Tokyo Electric Power Company, Yokohama,


    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP13643S