Host: The Japan Society of Mechanical Engineers
Name : The 30th International Conference on Nuclear Engineering (ICONE30)
Date : May 21, 2023 - May 26, 2023
The SPECTRA code has been developed as an integrated safety analysis tool for comprehensive analyses of in- and ex-vessel phenomena during a severe accident (SA) in a sodium-cooled fast reactor (SFR). The individual modules, such as sodium fire and sodium-concrete reaction, have been implemented into SPECTRA to simulate specific phenomena in an accident of SFRs. However, SPECTRA has no capability for the overlapped event involving sodium fire and sodium-concrete reaction because the sodium pool and the floor concrete are modeled in each module independently. 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. SPECTRA can simulate a reasonable heat and mass transfer behavior.
