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Neutron Flux and Void Distribution in BWR
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- KAWAI T.
- Hitachi, Ltd., Central Res. Lab.
Bibliographic Information
- Other Title
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- 沸騰水型原子炉における中性子束およびボイド分布
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Description
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.
Journal
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- Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan
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Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan 1 (1), 28-39, 1959
Atomic Energy Society of Japan
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Keywords
Details 詳細情報について
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- CRID
- 1390282681527408256
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- NII Article ID
- 130003746212
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- ISSN
- 21865256
- 00047120
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- Text Lang
- ja
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- Data Source
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- JaLC
- Crossref
- CiNii Articles
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- Abstract License Flag
- Disallowed