OS8-04 稠密37本バンドル熱特性試験とギャップ幅効果の評価(OS8 軽水炉・新型炉・核燃料サイクル)

概要

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A thermal/hydraulic feasibility project for Reduced-Moderation Water Reactor (RMWR) was started since 2002. In this R&D project, large-scale thermal-hydraulic tests, several model experiments and development of advanced numerical analysis codes are being carried out. In this paper, results of the large-scale thermal-hydraulic tests which simulate the RMWR bundle are summarized. Especially, gap width effect on critical power which was investigated using two 37-rod bundle test sections with 1.3 and 1.0mm in gap width is reported. As a result, it is confirmed that (1) fundamental characteristics of flow parameter impact on critical power are similar between the results using two test sections with 1.3mm and 1.0mm in gap width, (2) effect of cross-sectional power distribution could be expressed by the power factor of subchannel where BT (Boiling Transition) would occur, (3) quasi-steady-state predictive method for BT is applicable for postulated transients and (4) proposed evaluation method of pressure drop could yield good predictions in the tight-lattice bundle.
社団法人日本機械学会の論文
2005-06-28