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Physics Studies on BWR Void Simulated Cores, (I)
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- KIKUCHI Hiroshi
- Ozenji Div., Central Research Laboratory, Hitachi Ltd.,
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- FUJII Masaaki
- Ozenji Div., Central Research Laboratory, Hitachi Ltd.,
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- KIYOKAWA Kazuhiro
- Ozenji Div., Central Research Laboratory, Hitachi Ltd.,
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- OHNISHI Tadahiro
- Ozenji Div., Central Research Laboratory, Hitachi Ltd.,
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- KOBAYASHI Setsuo
- Ozenji Div., Central Research Laboratory, Hitachi Ltd.,
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Description
In an attempt to obtain more information concerning steam void effects on the physical behavior of BWR cores, voids ranging from zero to 24% volume fractions were statically simulated by inserting polyethylene tubes between fuel rods of simulated BWR core, and measurements were made of local flux distribution, neutron spectrum, reactivity, reactivity coefficient of void and so forth. The results were compared with calculations. Improved methods of calculation were developed, which assured better agreement with measured results.<BR>While this paper only deals with local distributions of the thermal neutron flux and spectrum within the assembly cells, it has been shown that spectrum variation near water gaps could be well described by an overlapping model which provided an improvement on the analysis. An additional improvement was obtained by the incorporation of an approximate transport correction.
Journal
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- Journal of Nuclear Science and Technology
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Journal of Nuclear Science and Technology 6 (8), 458-465, 1969
Atomic Energy Society of Japan
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Details 詳細情報について
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- CRID
- 1390282679075267584
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- NII Article ID
- 130000824024
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- COI
- 1:CAS:528:DyaF1MXkvFOgtbs%3D
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- ISSN
- 18811248
- 00223131
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- Text Lang
- en
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- Data Source
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- JaLC
- Crossref
- CiNii Articles
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- Abstract License Flag
- Disallowed