Effect on source term of containment bypass releases by different aerosol deposition model

A new aerosol deposition model of the secondary steam generator (SG) is developed for the complex flow path configuration and the new model is integrated into the severe accident analysis code. The integrated safety analysis model for 600 MW nuclear power plant with the new aerosol deposition model is built. The accident sequence of steam generator tube rupture (SGTR) and the bypass containment accidents are analyzed with the old model ana the new model. The results show that more fission products deposit in the secondary of the SG and the fractions of the fission products releasing to the environment with the new model decreases 26.6∼71.1% for the containment bypass release category. (authors)