ISFSI site boundary radiation dose rate analyses.
Across the globe nuclear utilities are in the process of designing and analysing Independent Spent Fuel Storage Installations (ISFSI) for the purpose of above ground spent-fuel storage primarily to mitigate the filling of spent-fuel pools. Using a conjoining of discrete ordinates transport theory (DORT) and Monte Carlo (MCNP) techniques, an ISFSI was analysed to determine neutron and photon dose rates for a generic overpack, and ISFSI pad configuration and design at distances ranging from 1 to -1700 m from the ISFSI array. The calculated dose rates are used to address the requirements of 10CFR72.104, which provides limits to be enforced for the protection of the public by the NRC in regard to ISFSI facilities. For this overpack, dose rates decrease by three orders of magnitude through the first 200 m moving away from the ISFSI. In addition, the contributions from different source terms changes over distance. It can be observed that although side photons provide the majority of dose rate in this calculation, scattered photons and side neutrons take on more importance as the distance from the ISFSI is increased.
Hagler
R J
RJ
Westinghouse Electric Co. LLC, PCAM/Radiation Analysis, Waltz Mill Site, P.O. Box 158, Madison, PA 15663, USA. haglerrj@westinghouse.com
Fero
A H
AH
D003198:Computer Simulation; D019544:Equipment Failure Analysis; D015233:Models, Statistical; D009010:Monte Carlo Method; D009502:Neutrons; D009688:Nuclear Reactors / Q000295:instrumentation*; D017785:Photons; D011829:Radiation Dosage; D011834:Radiation Monitoring / Q000379:methods* / Q000592:standards; D011835:Radiation Protection / Q000295:instrumentation* / Q000379:methods; D011850:Radioactive Waste / Q000032:analysis*; D012542:Scattering, Radiation; D018505:Waste Management / Q000295:instrumentation* / Q000379:methods
D011850:Radioactive Waste