Validation of STRCS code for calculation of fission-product transport in reactor coolant system during severe accidents

Transport and deposition of fission products within the primary coolant circuit during severe accident condition have significant effect on the amount of released radionuclides in the containment. In this study, a new code, STRCS, compatible with RELAP5/SCDAP code, has been developed that calculates the fission products' transport through the piping system. The homogeneous and heterogeneous nucleation, aerosol agglomeration, aerosol and vapor deposition and aerosol resuspension are considered in this code. The developed code was validated through international standard problems STROM SR11 and PHEBUS FPT-1 experiments. The STRCS predictions are in good agreement with the ISPs published results, although the obtained results deviate from the PHEBUS FPT-1 experimental data.