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류강우,이세종,김혁재,김광표 (사)한국방사선산업학회 2021 방사선산업학회지 Vol.15 No.2
In Korea, in order to complete the decommissioning of the nuclear facility, radiationdose due to residual radioactivity in the site or remaining buildings following (dose based)decommissioning satisfy site reuse criteria. When safety assessment of site reuse after decommissioning,site specific parameter should be used for reliable assessment. In this study, the sensitivityanalysis of the distribution coefficient, transfer factors, and bioaccumulation factor, which are themajor site specific parameter for the safety assessment were performed. The nuclides were selectedbased on decommissioning cases of overseas NPP, and 12 of the total 13 nuclides were selected asthe target nuclides. Resident farmer scenario was applied as an exposure scenario. Distributioncoefficient, transfer factors, and bioaccumulation factor were selected for sensitivity analysis. NDD(Normalized Dose Difference) was used as a sensitivity analysis method. For the application ofNDD, the statistical distribution presented in NUREG/CR-6697 was used. The 5th percentile wasapplied as the low value, the mean value was applied as the base value, and the 95th percentile wasapplied as the high value. As a result of sensitivity analysis, it was found that the contaminatedlayer distribution coefficient was sensitive to 99Tc and 90Sr. The distribution coefficients of theunsaturated and saturated layers were found to be insensitive to all nuclides. When the site has onesoil texture, the distribution coefficient was sensitive to 14C, 90Sr, 99Tc, and 241Am. In the case of planttransfer factor, it was sensitive to 63Ni, 90Sr, 99Tc, 238Pu, 241Am, and 241Pu. Meat transfer factor wassensitive to 55Fe, and milk transfer factor was sensitive to 63Ni. The bioaccumulation factor for fishwas insensitive to all nuclides. As a result of the sensitivity analysis, it was found that the degree ofsensitivity of the distribution coefficient and the transfer factor varies depending on the nuclide. Anddistribution coefficient and the transfer factor have a large influence on the change in the maximumdose overall. Therefore, in order to evaluate the safety of site reuse after decommissioning of nuclearfacilities, it is considered that reliable results can be derived only when the site-specific parametersare obtained and reflected in the evaluation.