STP1490: Influence of the Multigroup Approximation on VVER-1000 RPV Neutron/Gamma Flux Calculation

    Belousov, Sergey I.
    Senior Research Scientist, Scientific Researcher, Ph.D. Student, and Senior Research Scientist, Institute for Nuclear Research and Nuclear Energy of Bulgarian Academy of Science, Sofia,

    Kirilova, Desislava L.
    Senior Research Scientist, Scientific Researcher, Ph.D. Student, and Senior Research Scientist, Institute for Nuclear Research and Nuclear Energy of Bulgarian Academy of Science, Sofia,

    Mitev, Mladen R.
    Senior Research Scientist, Scientific Researcher, Ph.D. Student, and Senior Research Scientist, Institute for Nuclear Research and Nuclear Energy of Bulgarian Academy of Science, Sofia,

    Ilieva, Krassimira D.
    Senior Research Scientist, Scientific Researcher, Ph.D. Student, and Senior Research Scientist, Institute for Nuclear Research and Nuclear Energy of Bulgarian Academy of Science, Sofia,

    Pages: 6    Published: Jan 2007


    Abstract

    One-dimensional calculations of neutron and gamma group fluxes and radiation damage in terms of DPA have been carried out for VVER-1000 mock-up realized at LR-0 critical assembly, Rez, Czech Republic in order to evaluate the influence of energy dependence multigroup approximation on VVER-1000 RPV Neutron/Gamma flux calculation. Two calculational methods have been applied: Monte Carlo method (MC) with continuous energy dependence description and discrete ordinates (DO) method with multigroup energy dependence approximation. Two different multigroup neutron/gamma cross section libraries have been used: BGL1000—created especially for VVER-1000 application and BUGLE96—created for PWR application. A good consistency between the results for both methods and different cross section libraries is obtained for neutrons with energy above 0.1 MeV. The worst consistency is obtained for the thermal neutrons. For gammas a better consistency between DO and MC results is obtained when BGL1000 library is applied.

    Keywords:

    neutron fluence, reactor pressure vessel, radiation damage, multigroup approximation


    Paper ID: STP45453S

    Committee/Subcommittee: E10.02

    DOI: 10.1520/STP45453S


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