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)

概要

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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.
社団法人日本機械学会の論文
2006-06-28