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.
|出版ステータス||出版済み - 1 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 17 2015 → 5 21 2015
|その他||23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015|
|Period||5/17/15 → 5/21/15|
All Science Journal Classification (ASJC) codes
- Nuclear Energy and Engineering