Analysis of BWR Station Blackout Accident Thermal-Hydraulic Behavior up to Severe Core Damage in Fukushima Daiichi Power Plant Unit 2

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  • ＢＷＲ全電源喪失事故の解析　　福島第１発電所２号機における炉心損傷までの熱水力挙動
  • 福島第一原子力発電所事故関連論文 BWR全電源喪失事故の解析 : 福島第1発電所2号機における炉心損傷までの熱水力挙動
  • フクシマ ダイイチ ゲンシリョク ハツデンショ ジコ カンレン ロンブン BWR ゼン デンゲン ソウシツ ジコ ノ カイセキ : フクシマ ダイ1 ハツデンショ 2ゴウキ ニ オケル ロシン ソンショウ マデ ノ ネッスイリョク キョドウ

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Abstract

  The analysis of the long-term station blackout accident of BWR has been performed using the TRAC-BF1 code. The actuation of RCIC was assumed, and the results were compared with the data observed at the Fukushima Daiichi power plant unit 2 reactor. BWR-5 of 1,100 MW was analyzed, while the unit 2 reactor was BWR-4 of 780 MW. The reactor pressure and the core liquid level were, however, in good agreement with the observed data. It was confirmed that the quasi-steady state continued for a long time with the RCIC actuation. The timing of recovery action, which was composed of depressurization and coolant injection, necessary for the maximum clad temperature being less than 1,500 K was studied and compared with that of the unit 2 reactor.<br>

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