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A study on the dose evaluation of critical groups for unrestricted reuse of the site after the decommissioning of Kori Unit 1

In the calculation of DCGLs using RESRAD code, the selection of input parameter values is paramount, which is basically possible when specific measures for selecting reuse scenarios and probabilistic evaluation methods are established. When referring to the impact of the age group considered in the environmental impact assessment among the existing operations of the plant, it may also need to be applied in the decommissioning project, and there will be considerations along with site reuse scenarios and probabilistic evaluations. Therefore, the main purpose of this study is to distinguish the types of exposure affected by residual radioactivity contamination during the process of deriving DCGL to be used in the final site release stage of NPPs and to evaluate them by reasonably assigning age group parameter values. In addition, the case of entering a single value for parameter values by age group and the case of entering probabilistic distributions were compared and analyzed.
TK9001-9401, RESRAD, Age group, Site release, Site reuse scenario, Nuclear engineering. Atomic power, DCGL, Decommissioning
TK9001-9401, RESRAD, Age group, Site release, Site reuse scenario, Nuclear engineering. Atomic power, DCGL, Decommissioning
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