沸騰水型原子炉における中性子束およびボイド分布

DOI

書誌事項

タイトル別名
  • Neutron Flux and Void Distribution in BWR

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説明

In a large boiling water reactor, the power distribution is highly sensitive to the void distribution, and their mutual interaction is the most characteristic and important problem in the statics of BWR. Different methods are introduced to solve the two group diffusion equations, which involve the mutual interaction of the power, void and control rods distribution. In the numerical examples of typical cases by digital computer (HIPAC-1 and IBM-650) calculations given here, the results of one-dimensional forward method, backward method and two-dimensional backward method are compared. The “Peaceman-Rachford” method is used to accelerate the convergence in the two-dimensional backward method. The utility of the backward method is particularly evident in two-dimensional studies, however, the correlative application of the forward method with the backward method, seems to be necessary in the actual design of large boiling water reactors.

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詳細情報 詳細情報について

  • CRID
    1390282681527408256
  • NII論文ID
    130003746212
  • DOI
    10.3327/jaesj.1.28
  • ISSN
    21865256
    00047120
  • 本文言語コード
    ja
  • データソース種別
    • JaLC
    • Crossref
    • CiNii Articles
  • 抄録ライセンスフラグ
    使用不可

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