Volume 3, Issue 3 (March 2006)

    Benchmark on the 3-D VENUS-2 MOX-Fueled Reactor Dosimetry Calculations by DANTSYS Code System

    (Received 20 June 2005; accepted 29 September 2005)

    Published Online: 2005

    CODEN: JAIOAD

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    Abstract

    The benchmark calculation for the 3-D VENUS-2 MOX-fueled reactor dosimetry has been performed by the TRANSX/DANTSYS code system. The nuclear data from the ENDF/B-VI.8, JENDL-3.3, and JEFF-3.0 have been processed for the MATXS-format 199-group neutron libraries by NJOY99.90. The equivalent fission fluxes at the 34 measurement positions on the core mid-plane have been calculated using the dosimetry reaction rates for the 58Ni(n,p), 115In(n,n'), 103Rh(n,n'), 64Zn(n,p), 237Np(n,f), and 27Al(n,α) detectors. The estimated results by the JENDL-3.3 and JEFF-3.0 have been compared with those by the ENDF/B-VI.8.


    Author Information:

    Kim, DH
    Senior Researcher and Principal Researchers, Korea Atomic Energy Research Institute, Yuseong, Daejeon,

    Gil, C-S
    Senior Researcher and Principal Researchers, Korea Atomic Energy Research Institute, Yuseong, Daejeon,

    Chang, J
    Senior Researcher and Principal Researchers, Korea Atomic Energy Research Institute, Yuseong, Daejeon,


    Stock #: JAI13454

    ISSN: 1546-962X

    DOI: 10.1520/JAI13454

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    Author
    Title Benchmark on the 3-D VENUS-2 MOX-Fueled Reactor Dosimetry Calculations by DANTSYS Code System
    Symposium Reactor Dosimetry, 12th Volume, 2005-05-13
    Committee E10