Development of the ex-vessel modules for the integrated SFR safety analysis code SPECTRA

Aoyagi, Mitsuhiro ; Makino, Toru*; Oki, Hiroshi*; Uchibori, Akihiro ; Okano, Yasushi

The SPECTRA code has been developed as an integrated safety analysis tool for sodium-cooled fast reactors (SFRs). In this study, the capability of SPECTRA is enhanced by integrating the analyses of sodium pool fire and concrete ablation for overlapped events of the ex-vessel phenomena. The sodium pool fire module is connected to the shared module for the sodium pool and the floor concrete developed in our previous study. The developed model is validated through the benchmark analysis of the F7-1 pool fire experiment. The calculation result of the pool and catch pan temperature shows good agreement with the experimental data. A demonstration analysis is also conducted for an overlapped event of the ex-vessel phenomena.