Scrutiny of Radiation Exposure due to Accident ofDropping two Fuel Assemblies into the Spent FuelPool of Reactor Building in Bushehr NuclearPower Plant During Nuclear Fuel Transportation

In this research, Maximum Radiation Exposure dose is calculated for the Accident of Fuel handling duringLoading Fuel Assembly in spent Fuel pool due to Drop of a Fuel Assembly during its reloading to SpentFuel Pool in Bushehr Nuclear Power Plant from the view point of radio nuclides release to the environment.Calculations are performed using a Gaussian Diffusion model [۳,۴] and a slightly modified version ofAIREM computer code [۶] to adopt for conditions in Bushehr. The results are comparable with the Finalsafety analysis report [۲] which used DOZAM code [۷]. Result of our calculations shows no excessive dosein populated regions. Maximum Activities due to fission products released in Spent Fuel Pool werecalculated ۲*۱۰۰۹ Bq/Kg (by AIREM Code) and ۱.۴*۱۰۰۹ by DOZAEM Code (Figs.۲,۳). MaximumActivities due to Radionuclides Released to Steel Containment were calculated by Codes as ۴.۵*۱۰۱۴,۳*۱۰۱۴ respectively (Figs.۴,۵,۶). Maximum Activities due to Radionuclides Released to EnvironmentDuring Short-Term in Accident by AIREM & DOZAEM ۲*۱۰۱۰, ۷*۱۰۰۹ respectively were calculated(Figs.۸,۹). The Results are comparable with the Final Safety Analysis Report (FSAR)which used DOZAEMcode [۲,۷]. According to the above calculations we have no Excessive Radiation Exposure to Receptors(Operators, Skill Workers & People) during the Accident involving Dropping of Fuel Assemblies into theSpent Fuel Pool of BNPP-۱.