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受動的安全性を有する原子炉圧力容器冷却設備の伝熱特性に関する研究; スケールモデルによる実験的検討

Study on heat transfer characteristics of reactor cavity cooling system with passive safety features; Experimental investigation using a scaled model

山口 修平*; 佐藤 紀恭*; 松元 達也*; 守田 幸路*; 高松 邦吉

Yamaguchi, Shuhei*; Sato, Noriyasu*; Matsumoto, Tatsuya*; Morita, Koji*; Takamatsu, Kuniyoshi

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、動的機器およ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。本研究では、この冷却設備の伝熱特性を把握するために伝熱試験装置を製作し、基礎的な実験を行った。その結果、ふく射によって原子炉圧力容器からの熱を受動的に除去できることを定量的に評価できた。

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. The RCCS can always stably and passively remove a part of the released heat at the rated operation and the decay heat after reactor shutdown. In 205, we built the scale-down heat removal test facility and now conduct experiments to understand the heat-transfer characteristics. As a result, we could assess effect of radiation quantitatively for passive decay heat removal from the RPV.

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