Radiation release characterization of PWR spent fuel assemblies generated from Korean nuclear power plants
Moon Hyun Joo
Nuclear Technology and Radiation Protection · 2009
doi:10.2298/ntrp0903183m (opens in a new tab)
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Abstract
Spent nuclear fuel should be kept under safe management until it is disposed of permanently. Because of this, it is important to understand its radiation release characteristics. In this paper, the Monte Carlo method is applied to evaluate the radiation release characteristics of two types of PWR spent fuel assembly generated from the operating plants in Korea: Westinghouse and Korea Standard Nuclear Power Plant. The source terms were calculated using ORIGEN-ARP. The neutron and photon (or gamma) dose distributions along the vertical and horizontal directions of each spent fuel assembly were evaluated using MCNPX code. Compared with the two dose distributions, the photon dose was found to be about 105 times higher than the neutron dose.
Abstract licence: CC BY-NC-ND
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