Development of Design Technology on Thermal-Hydraulic Performance in Tight-Lattice Rod Bundles: I-Master Plan and Executive Summary
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概要
- 論文の詳細を見る
R&D project to investigate thermal-hydraulic performance in tight-lattice rod bundles for Innovative Water Reactor for Flexible Fuel Cycle has been progressed at Japan Atomic Energy Agency in collaboration with power utilities, reactor vendors and universities since 2002. In this series-study, we will summarize the R&D achievements using large-scale test facility (37-rod bundle with full-height and full-pressure), model experiments and advanced numerical simulation technology. This first paper described the master plan for the development of design technology and showed an executive summary for this project up to FY2005. The thermal-hydraulic characteristics in the tight-lattice configuration were investigated and the feasibility was confirmed based on the experiments. We have developed the design technology including 3-D numerical simulation one to evaluate the effects of geometry/scale on the thermal-hydraulic behaviors.
- 一般社団法人 日本機械学会の論文
著者
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Tamai Hidesada
Japan Atomic Energy Agency
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Ohnuki Akira
Japan Atomic Energy Agency
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Liu Wei
Japan Atomic Energy Agency
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Akimoto Hajime
Japan Atomic Energy Agency
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KURETA Masatoshi
Japan Atomic Energy Agency
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Takase Kazuyuki
Japan Atomic Energy Agency Nuclear Science And Engineering Directorate
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Yoshida Hiroyuki
Japan Atomic Energy Agency
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MISAWA Takeharu
Japan Atomic Energy Agency
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LIU Wei
Japan Atomic Energy Agency (JAEA)
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