Volume 3, Issue 7 (July 2006)

    Benchmarking of PENTRAN-SSN Parallel Transport Code and FAST Preconditioning Algorithm Using the VENUS-2 MOX-Fueled Benchmark Problem

    (Received 20 June 2005; accepted 19 April 2006)

    CODEN: JAIOAD

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    Abstract

    The discrete ordinates method (Sn) is the most widely used technique to obtain numerical solutions of the linear Boltzmann equation, and therefore to evaluate radiation fields and dose rates in nuclear devices. However, it is well known that this method suffers from slow convergence for problems characterized by optically thick media and scattering ratio close to unity. To address this issue we have developed a new preconditioning algorithm based on the even-parity simplified Sn (EP-SSN) equations. The new method is based on the flux acceleration simplified transport (FAST) algorithm which is implemented into the PENTRAN-SSN code system. The code system is designed for parallel computing architectures; PENTRAN-SSN features spatial, angular, and energy domain decomposition algorithms. The FAST preconditioner is parallelized with a spatial domain decomposition algorithm. In this paper, our objective is to test the performance of the new preconditioning system for a three-dimensional shielding calculation based on the VENUS-2 MOX-fueled benchmark problem, issued by OECD/NEA (Organization for Economic Co-operation and Development/Nuclear Energy Agency.


    Author Information:

    Longoni, G
    Senior Engineer, Westinghouse Electric Co. LLC, Madison, PA

    Haghighat, A
    Professor and Chair, Nuclear and Radiological Engineering, University of Florida, Gainesville, FL

    Yi, C
    Graduate Student, Nuclear and Radiological Engineering, University of Florida, Gainesville, FL

    Sjoden, GE
    Professor, Nuclear and Radiological Engineering, University of Florida, Gainesville, FL


    Stock #: JAI13428

    ISSN: 1546-962X

    DOI: 10.1520/JAI13428

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    Author
    Title Benchmarking of PENTRAN-SSN Parallel Transport Code and FAST Preconditioning Algorithm Using the VENUS-2 MOX-Fueled Benchmark Problem
    Symposium Reactor Dosimetry, 12th International Symposium, 2005-05-13
    Committee E10