102 0 0 0 OA 122. 炉心溶融事故時の格納容器内熱水力挙動の感度解析
- 著者
- 小林 健介 堀井 英雄 石神 努 千葉 猛美
- 出版者
- 一般社団法人 日本原子力学会
- 雑誌
- 日本原子力学会誌 (ISSN:00047120)
- 巻号頁・発行日
- vol.27, no.1, pp.56-65, 1985-01-30 (Released:2009-04-21)
- 参考文献数
- 10
- 被引用文献数
- 1 1
A sensitivity analysis of thermal hydraulic response in containment during a 'station blackout' (the loss of all AC power) accident at Browns Ferry unit one plant was performed with the computer code MARCH 1.0. In the analysis, the plant station batteries were assumed to be available for 4h after the initiation of the accident. The thermal hydraulic response in the containment was calculated by varying several input data for MARCH 1.0 independently and the deviation among calculated results were investigated.The sensitivity analysis showed that (a) the containment would fail due to the overtemperature without any operator actions for plant recovery, which would be strongly dependent on the model of the debris-concrete interaction and the input parameters for specifying the containment failure modes in MARCH 1.0, (b) a core melting temperature and an amount of water left in a primary system at the end of the meltdown were identified as important parameters which influenced the time of the containment failure, and (c) experimental works regarding the parameters mentioned above could be recommended.
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福島原子力事故の前から、単にそれだけの話ですね。
（例）炉心溶融事故時の格納容器内熱水力挙動の感度解析
https://t.co/SzQfQdkvgh
「炉心溶融事故＝Core Meltdown Accident」
https://t.co/8qEyTIv4ec
一例は↓
https://t.co/ny0vVn3Xvu
「炉心溶融事故」が英文では "Core Meltdown Accident"となっています。あえて区別してより正確に書くならば、この論文中にあるように"meltdown"（メルトダウン）とは「溶融炉心の圧力容器底部落下」を表すものであり、水蒸気爆発を直接意味するものではない。
日本原子力学会誌の論文例（無料） https://t.co/nLVcmdBzCY https://t.co/1Wt8bR8sVf https://t.co/j87tTRJ2Ch https://t.co/9plsuPx56e @DonnieTheDutch @kikumaco