A study on characteristics of molten pool sloshing in core disruptive accidents of fast reactors

Isao Tatewaki, Koji Morita, Hiroshi Endo

研究成果: 会議への寄与タイプ学会誌査読

4 被引用数 (Scopus)

抄録

To understand the mechanism of maximum energy released in core disruptive accidents (CDAs) of sodium-cooled fast reactors (SFRs), we investigated behavior of whole core molten fuel pool using a fast reactor safety analysis code. Several high reactivity insertions and power peaks due to super prompt criticality appears by radial pool sloshing motion. We noticed that the pool motion suppressed at the super prompt criticality in series of analysis. We called this suppression phenomenon as "mitigation effect". It is caused by fuel vapor pressure due to a rise in fuel temperature. By this effect, the reactivity ramp rate and inserted reactivity are restrained. It is expected that the existence of the mitigation effect becomes a clue in quantifying an upper limitation of the released energy.

本文言語英語
出版ステータス出版済み - 1月 1 2015
イベント23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015 - Chiba, 日本
継続期間: 5月 17 20155月 21 2015

その他

その他23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015
国/地域日本
CityChiba
Period5/17/155/21/15

All Science Journal Classification (ASJC) codes

  • 原子力エネルギーおよび原子力工学

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