- 著者
-
渡辺 正
石垣 将宏
佐藤 聡
中村 秀夫
- 出版者
- Atomic Energy Society of Japan
- 雑誌
- 日本原子力学会和文論文誌 (ISSN:13472879)
- 巻号頁・発行日
- vol.10, no.4, pp.240-244, 2011 (Released:2011-11-30)
- 参考文献数
- 4
- 被引用文献数
-
2
2
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.