Estimation of Source Term Release to Environment in Three Severe Accident Scenarios in Typical PWR and Comparison with Other Research or Accidents

This paper provides insights into the radiological impacts of three typical severe accident scenarios of OPR-1000 nuclear power plants. Three severe accident scenarios analyzed are (1) Station Blackout (SBO) without recovery of AC and DC powers longer than a few days as occurred in Fukushima accident, (2) Steam generator tube rupture (SGTR), and (3) Interfacing systems Loss of coolant accident (ISLOCA). Fission products released from core are released to containment by cyclic opening and closure of PORV after the fuel cladding damage occurs and then released to environment by overpressure of the containment in SBO accident sequence. SGTR and ISLOCA accidents are bypass sequences where the fission products released from the core to RCS released directly to the environment bypassing containment. Severe accident source term estimation is needed for the establishment of emergency response preparedness. This paper provides insights into the radiological impacts of three typical severe accident scenarios of OPR-1000 nuclear power plants. Three severe accident scenarios analyzed are (1) Station Blackout (SBO) without recovery of AC and DC powers longer than a few days as occurred in Fukushima accident, (2) Steam generator tube rupture (SGTR), and (3) Interfacing systems Loss of coolant accident (ISLOCA). Fission products released from re are released to containment by cyclic opening and closure of PORV after the fuel cladding damage occurs and then released to environment by overpressure of the containment in SBO accident sequence.