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Nuclear Emergency Management using Accident Consequence Analysis Code
Borhan Uddin Gazi Muhammad,김주열 한국방재학회 2019 한국방재학회논문집 Vol.19 No.4
Shin Kori Unit 3 is a new pressurized water reactor in Advanced Power Reactor 1400, which was developed by Korea Hydro and Nuclear Power Co. and commenced commercial operation in December 2016. We calculated the radionuclide concentrations and related radiation doses at the early stage of accidents under the assumption of hypothetical severe nuclear accidents in Shin Kori Unit 3. In this study, the radiological source terms of the accident scenarios were evaluated using the radiological assessment system for consequence analysis code, which has been used as a regulatory software tool for emergency response applications developed by the United States Nuclear Regulatory Commission. In general, the atmospheric transport, dispersion, and deposition processes of radioactive materials can be simulated by the Gaussian model using a straight-line trajectory Gaussian plume model for short distances and a Lagrangian Gaussian puff model for long distances. The most dangerous scenarios were observed during winter when we considered two accident scenarios, namely, long-term station blackout (LTSBO) and loss-of-coolant accident (LOCA), based on the reactor conditions and seasonal effects. The total effective dose equivalent values for LTSBO and LOCA were estimated to be 14 and 0.08 mSv, respectively, in the precautionary action zone of 5 km in two days after the accident. According to Korean regulations on urgent public protective actions, the criteria are 10 mSv in two days for indoor sheltering and 50 mSv in one week for public evacuation. In the LTSBO case, we found that immediate public protective measures were required. Appropriate decisions must be made by the off-site emergency management center under the Nuclear Safety and Security Commission in Korea.