1. Model integration of the ex-vessel modules for the SFR safety analysis code SPECTRA
- Author
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Mitsuhiro AOYAGI, Tohru MAKINO, Hiroshi OHKI, Akihiro UCHIBORI, and Yasushi OKANO
- Subjects
sodium-cooled fast reactor ,severe accident ,sodium chemistry ,computational evaluation ,spectra ,Mechanical engineering and machinery ,TJ1-1570 - Abstract
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 in the same compartment because the sodium pool and the floor concrete are modeled in each module independently. 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. A new shared module for the sodium pool and floor concrete region, named “PFC module” was introduced in the previous study. The sodium fire module is connected to the PFC module in this study. The integrated model is validated through the benchmark analysis of the F7-1 pool fire experiment. The calculation results of the temperature and combustion rate show good agreement with the experimental result. A demonstration analysis is also conducted for an overlapped event of the ex-vessel phenomena including both concrete ablation and sodium pool fire. SPECTRA can simulate a reasonable heat and mass transfer behavior during the overlapped event.
- Published
- 2024
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