سال انتشار: ۱۳۸۵
محل انتشار: همایش بین المللی جایگاه چرخه سوخت هسته ای در توسعه فن آوری و تحقیقات
تعداد صفحات: ۱
Haghighi shad – Ofogh Consulting Engineers-Boshehr Nuclear Power Plant- Unit-l(BWPP)
Davilu – Amirkabir Ind. University
Sharifi – Ofogh Consulting Engineers-Boshehr Nuclear Power Plant- Unit-l(BWPP)
Khodadadi – AEOI, Specialist of y Radiation Center , Tehran
In this research, Maximum Radiation Exposure dose is calculated for the Accident of Fuel handling during Loading Fuel Assembly in spent Fuel pool due to Drop of a Fuel. Assembly during its reloading to Spent Fuel Pool in Bushehr Nuclear Power Plant from the view point of radio nuclides release to the environment. Calculations are performed using a Gaussian Difhsion mode1[3,4] and a slightly modified version of AIREM computer code to adopt for conditions in Bushehr. The results are comparable with the Final safety analysis report which used DOZAM code. Result of our calculations shows no excessive dose in populated regions. Maximum Activities due to fission products released in Spent Fuel Pool were calculated 2*1009 Bq/Kg (by AIREM Code) and 1.4*1009 by DOZAEM Code(Figs.2,3). Maximum Activities due to Radionuclides Released to Steel Containment were calculated by Codes as 4.5*1014, 3* 1014 respectively(Figs.4,5,6). Maximum Activities due to Radionuclides Released to Environment During Short-Tern in Accident by AIREM 8r. DOZAEM 2" 1010 , 7* 1009 respectively were calculated( Figs.8,9). The Results are comparable with the Final Safety Analysis Report(FSAR)which used DOZAEM code[2,7]. According to the above calculations we have no Excessive Radiation Exposure to Receptors(Operators, Skill Workers & People) during the Accident invclving Dropping of Fuel Assembiies into the Spent Fuel Pool of BNPP-1.