検索対象:     
報告書番号:
※ 半角英数字
 年 ~ 
 年

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

Analysis of BWR station blackout accident; Thermal-hydraulic behavior up to severe core damage in Fukushima Daiichi Power Plant Unit 2

渡辺 正; 石垣 将宏 ; 佐藤 聡 ; 中村 秀夫 

Watanabe, Tadashi; Ishigaki, Masahiro; Satou, Akira; Nakamura, Hideo

BWRの長時間に渡る全電源喪失事故の解析を、TRAC-BF1コードを用いて行った。RCICの作動のみを仮定し、福島第一原子力発電所2号機で観測されたデータと比較し、RCIC停止後の冷却回復操作の有効性を調べた。解析の対象は、110万KW級BWR-5としたが、原子炉圧力及び炉心水位変化のいずれも、78万KW, BWR-4である2号機のデータとよく一致した。これにより、RCICの連続的な運転により、準定常的な熱水力状態が長時間保たれたことが確認された。また、RCIC停止後に、減圧とそれに続く冷却水の注入を冷却回復操作として行う場合に、被覆管温度を1500K以下に保つために必要な操作開始時間を検討し、2号機の場合と比較した。

The analysis of long-term station blackout accident of BWR has been performed using TRAC-BF1 code. The actuation of RCIC was assumed, and the results were compared with the observed data at the Fukushima Daiichi power plant unit 2 reactor. The effectiveness of recovery action for reactor cooling was discussed after the termination of RCIC. A BWR-5 with 1100 MW was analyzed, while the unit 2 was a BWR-4 with 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 was continued for a long time by the RCIC actuation. The timing of recovery action, which is composed of depressurization and coolant injection, necessary for the clad temperature being less than 1500 K was studied and compared with the unit 2.

Access

:

- Accesses

InCites™

:

Altmetrics

:

[CLARIVATE ANALYTICS], [WEB OF SCIENCE], [HIGHLY CITED PAPER & CUP LOGO] and [HOT PAPER & FIRE LOGO] are trademarks of Clarivate Analytics, and/or its affiliated company or companies, and used herein by permission and/or license.