STP1550

    Development of for Inspection of Spent Fuel Pool

    Published: Aug 2012


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    Abstract

    In this paper, we discuss an accurate and fast software tool (, Inspection of Nuclear Spent fuel-Pool Calculation Tool, version Spreadsheet) developed for calculation of the response of fission chambers placed in a spent fuel pool, such as Atucha-I. is developed for identification of suspicious regions of the pool that may have missing or substitute assemblies. uses a hybrid algorithm based on the adjoint function methodology. The neutron source is comprised of spontaneous fission, (α, n) interactions, and subcritical multiplication. The former is evaluated using the code, and the latter is obtained with the fission matrix (FM) formulation. The FM coefficients are determined using the Monte Carlo code, and the importance function is determined using the 3-D parallel Sn code. Three databases for the neutron source, FM elements, and adjoint flux are prepared as functions of different parameters including burnup, cooling time, enrichment, and pool lattice size. uses the aforementioned databases and systems of equations to calculate detector responses, which are subsequently compared with normalized experimental data.

    Keywords:

    adjoint, subcritical, proliferation, spent fuel pool, fission matrix, Sn, Monte Carlo


    Author Information:

    Walters, William
    Nuclear Engineering Program, Mechanical Engineering Dept., Virginia Tech, Blacksburg, VA

    Haghighat, Alireza
    Nuclear Engineering Program, Mechanical Engineering Dept., Virginia Tech, Blacksburg, VA

    Sitaraman, Shivakumar
    Lawrence Livermore National Laboratory, Livermore, CA

    Ham, Young
    Lawrence Livermore National Laboratory, Livermore, CA


    Paper ID: STP155020120052

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP155020120052


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