主催: 一般社団法人 日本機械学会
会議名: 第25回 動力・エネルギー技術シンポジウム
開催日: 2021/07/26 - 2021/07/27
The SPECTRA code has been developed as an integrated simulation system for severe accident evaluation in a sodium cooled fast reactor. In this study, the sodium pool fire model of SPECTRA is accessed through the benchmark analysis of the F7-1 pool fire experiment. As well as the comparison with the experimental data, the SPECTRA result is also compared to the results of the MELCOR and SPHINCS codes. All the SPECTRA results well agree with the results of SPHINCS from which the pool fire model of SPECTRA is adapted. The comparisons with MELCOR and experiment show also reasonable agreements in the essential pool fire behavior. The principal difference is the combustion rare after sodium supply stopping especially in the comparison with the experiment. This affects smaller temperature decreasing of the pool, catch-pan, and gas in SPECTRA. Such differences should be investigated more in the future works.
