STP1490

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

    Published: Jan 2007


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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 27AI(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.

    Keywords:

    VENUS-2, DANTSYS, NJOY99.90, ENDF/B-VI.8, JENDL-3.3, JEFF-3.0, IRDF-90 version 2


    Author Information:

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

    Gil, Choong-Sup
    Senior Researcher and Principal Researchers, Korea Atomic Energy Research Institute, Yuseong, Daejeon,

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


    Paper ID: STP45428S

    Committee/Subcommittee: E10.02

    DOI: 10.1520/STP45428S


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