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

Isao Tatewaki, Koji Morita, Hiroshi Endo

Research output: Contribution to conferencePaper

2 Citations (Scopus)

Abstract

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.

Original languageEnglish
Publication statusPublished - Jan 1 2015
Event23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015 - Chiba, Japan
Duration: May 17 2015May 21 2015

Other

Other23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015
CountryJapan
CityChiba
Period5/17/155/21/15

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering

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    Tatewaki, I., Morita, K., & Endo, H. (2015). A study on characteristics of molten pool sloshing in core disruptive accidents of fast reactors. Paper presented at 23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015, Chiba, Japan.