Critical Power Evaluation with Consideration of Differences in Droplet Behavior due to Spacer Shape Influence.
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- KANAZAWA Toru
- Energy Research Laboratory, Hitachi Ltd.
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- NISHIDA Koji
- Energy Research Laboratory, Hitachi Ltd.
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- NAGAYOSHI Takuji
- Energy Research Laboratory, Hitachi Ltd.
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- KAWASAKI Terufumi
- Energy Research Laboratory, Hitachi Ltd.
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- YOKOMIZO Osamu
- Energy Research Laboratory, Hitachi Ltd.
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Abstract
An evaluation method for droplet deposition coefficients, corresponding to spacer shapes, was developed in order to predict nuclear fuel bundle critical power. The method is based on a three-dimensional numerical analysis of dispersed flow around the spacer. The analysis showed that coolant droplet deposition characteristics onto fuel rods differed between grid type and ferrule type spacers, and also between fuel rods due to flow tabs on the upper end of the spacer band. The droplet deposition coefficient was modeled from the analysis results and adopted into a critical power prediction code based on subchannel analysis. Comparisons between critical powers calculated by the subchannel analysis code and those measured with full-scale test assemblies showed good agreement and improved prediction accuracy of the code.
Journal
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- Journal of Nuclear Science and Technology
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Journal of Nuclear Science and Technology 32 (4), 301-312, 1995
Atomic Energy Society of Japan
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Keywords
Details 詳細情報について
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- CRID
- 1390282679072254464
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- NII Article ID
- 10002072352
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- NII Book ID
- AA00703720
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- COI
- 1:CAS:528:DyaK2MXltFaktbc%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