Effect of Neutron Anisotropic Scattering and Treatment of Angular Dependency of Neutron Flux in Effective Cross Section on Criticality in Fast Reactor Analysis

DOI
  • CHIBA Gou
    Oarai Eng. Center, Japan Nucl. Cycle Develop. Inst.

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Other Title
  • 高速炉炉心解析における中性子非等方散乱と実効断面積の中性子束角度依存性の取扱いの臨界性への効果

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Description

Numerical tests were performed about an effect of neutron anisotropic scattering and treatment of angular dependency of neutron flux in effective cross section on criticality based on previous researches. Three approximations described on a previous report were compared to each other in both one-dimensional slab model and two-dimensional cylindrical model. As a result, it was found that the transport approximation, which has been conventionally used in fast reactor analyses in Japan, has a good accuracy in criticality analyses of typical fast reactors. However, the transport approximation is not enough to calculate accurately cores which have fuel-reflector boundary. Therefore it is desirable that the extended transport approximation with higher order of anisotropic scattering is used in the analyses for such cores.

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Details 詳細情報について

  • CRID
    1390282680163350656
  • NII Article ID
    130003935955
  • DOI
    10.3327/taesj2002.3.200
  • COI
    1:CAS:528:DC%2BD2cXnvVKksbY%3D
  • ISSN
    21862931
    13472879
  • Data Source
    • JaLC
    • Crossref
    • CiNii Articles
  • Abstract License Flag
    Disallowed

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