Ohno, Shuji 
; Makino, Toru; Ono, Isao*; Seino, Hiroshi
The CONTAIN-LMR code is being developed in the Japan Atomic Energy Agency (JAEA) to utilize for the quantitative assessment of accident consequences considered in sodium-cooled fast reactor (SFR) plant. Out of various physical and chemical behaviors treated in the code, this paper describes sodium fire related study issues such as computational modeling and its validation activities with focusing on important evaluating targets. Sodium pool and spray fire model validation practices are presented through the numerical analyses of sodium leak and fire experiments performed in the SAPFIRE facility.
Language |
: | English |
|---|---|---|
Journal |
: | Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM) |
Volume |
: | |
Number |
: | |
Pages |
: | 5 Pages |
Publication Year/Month |
: | 2014/05 |
Meeting title |
: | 23rd International Conference on Nuclear Engineering (ICONE-23) |
Held date |
: | 2015/05 |
Location (city) |
: | Chiba |
Location (country) |
: | Japan |
Paper URL |
: |
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Keywords |
: | no keyword |
Accesses |
: |
- Accesses |
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Altmetrics |
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