OS8-3 Feasibility Study on Thermal-Hydraulic Performance in Tight-Lattice Rod Bundles (1) : 37-rod bundle tests and subchannel analysis
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- Tamai Hidesada
- JAEA
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- Kureta Masatoshi
- JAEA
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- Ohnuki Akira
- JAEA
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- Yoshida Hiroyuki
- JAEA
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- Sato Takashi
- JAEA
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- Liu Wei
- JAEA
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- Akimoto Hajime
- JAEA
Bibliographic Information
- Other Title
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- OS8-3 稠密格子炉心の除熱技術開発(1) : 37本バンドル熱特性試験の結果とNASCAによる解析的評価(OS8 軽水炉・新型炉・核燃料サイクル,分散と集中の共存)
Abstract
A thermal-hydraulic feasibility project for the Innovative Water Reactor for Flexible fuel cycle (FLWR) was started since 2002. In this R & D project, large-scale thermal-hydraulic experiments, several model experiments and development of advanced numerical analysis codes are being carried out. This paper describes results of the large-scale thermal-hydraulic experiments that simulate the tight-lattice bundle in the FLWR core and subchannel analyses for effects of gap width, bundle scale and rod bowing. As a result, it is confirmed that (1) fundamental characteristics of flow parameter impact on critical power can be evaluated by the subchannel analysis code, NASCA, (2) the increase of the number of rods in a bundle promotes the thermal performance to cool the fuel rods and (3) the critical power decreases with increasing the amount of the bowing.
Journal
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- The Proceedings of the National Symposium on Power and Energy Systems
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The Proceedings of the National Symposium on Power and Energy Systems 2006.11 (0), 195-196, 2006
The Japan Society of Mechanical Engineers
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Keywords
Details 詳細情報について
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- CRID
- 1390282680862576384
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- NII Article ID
- 110006637327
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- ISSN
- 24242950
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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