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受動的安全性を持つ新しい炉容器冷却設備,1; 実機のRCCSと比較するために等倍縮小した除熱試験装置の実験条件

New Reactor Cavity Cooling System (RCCS) having passive safety features, 1; Experimental conditions of a scale-down heat removal test facility for comparison with a real RCCS

高松 邦吉  ; 松元 達也*; 守田 幸路*

Takamatsu, Kuniyoshi; Matsumoto, Tatsuya*; Morita, Koji*

東京電力の福島第一原子力発電所事故(以下、福島事故)後、深層防護の観点から炉心損傷の防止対策が重要になった。そこで、動的機器及び非常用電源等を必要とせず、福島事故のようにヒートシンクを喪失することのない、受動的安全性を持つ原子炉圧力容器の冷却設備を提案する。また、本冷却設備の優れた除熱性能を示すために、伝熱試験装置を製作し、実験を開始した。さらに、実機の冷却設備のふく射及び自然対流を同時に再現できる方法を検討した結果、伝熱試験装置の実験条件を定める手法を提案できた。

After Fukushima Daiichi nuclear disaster by TEPCO, a cooling system to prevent core damage became more important from the perspective of defense in depth. Therefore, a new, highly efficient RCCS with passive safety features without a requirement for electricity and mechanical drive is proposed. Employing the air as the working fluid and the ambient air as the ultimate heat sink, the new RCCS design strongly reduces the possibility of losing the heat sink for decay heat removal. Now, we conduct experiments with the scale-down heat removal test facility to understand the heat-transfer characteristics and assessed effect of radiation quantitatively. Moreover, after considering experimental conditions for the scale-down heat removal test facility to reproduce radiation and natural convection in the new RCCS, we can also find decision technique for the experimental conditions.

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