摘要
Development and Validation of a New Domestic Software for Dose Assessment during Normal and Accident Conditions in Nuclear Power Plants(NPPS)Ali Haghighi Shad 1,Darioush Masti 2,Mitra Athari Allaf 1,Kamran Sepanloo 3,Seyed Amir Hossein Feghhi 4(1.Department of Nuclear Engineering,Science and Research Branch,Islamic Azad University,Tehran,Iran;2.Department of Nuclear Engineering,Bushehr Branch,Islamic Azad University,Boushehr,Iran;3.Reactor and Nuclear Safety School,Nuclear Science and Technology Research Institute(NSTRI),Tehran,Iran;4.Department of Radiation Application,Shahid Beheshti University,Tehran,Iran)Abstract:In this research,a comprehensive code called KIANA is developed based on the Gaussian plume model to simulate and predict the radiological consequences received through all the possible,reasonable,probable,and standard exposure pathways for NPPs and chemical facilities.To validate the KIANA code,a case study is modeled for Bushehr Nuclear Power Plant Unit One(BNPP-1),and the KIANA code results are compared with the results of the Final Safety Analysis Report(FSAR-2017)data of BNPP-1.To assess the performance of the KIANA code,the total dose due to the airborne pathway in accident conditions including small break LOCA(SBLOCA),large break LOCA(LBLOCA),and equivalent exposure dose for the thyroid gland of a group of infants and children age 1 to 8 y at BNPP-1,are investigated.The KIANA code results show that the total effective doses do not exceed the regulatory limit of 5 mSv for external and internal exposures and the regulatory limit of 50 mSv for thyroid equivalent dose.The KIANA code results indicate good agreement with the results of FSAR-2017.
出处
《辐射防护》
CAS
CSCD
北大核心
2022年第4期378-380,共3页
Radiation Protection
