A study on DCGL determination and the classification of contaminated areas for preliminary decommission planning of KEPCO-NF nuclear fuel fabrication facility

Cho, Seo-Yeon; Yong-Soo, Kim; Park, Da-Won; Park, Chan-Jun

doi:10.1016/j.net.2019.06.012

Cited by 4 publications

(1 citation statement)

References 3 publications

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“…In South Korea, which is about to decommission its first commercial nuclear power plant, Kori Unit 1, research on the exposure dose and DCGL using RESRAD is being actively conducted [4][5][6][7][8][9][10][11][12]. However, no accurate comparative analysis between deterministic and probabilistic analyses has been performed.…”

Section: Introductionmentioning

confidence: 99%

Comparative Analysis of Probabilistic Analysis and Deterministic Analysis by RESRAD Code

2020

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The decommissioning of nuclear facilities indicates that the site is finally released according to a limited or unlimited site reuse purpose. In this process, the assessment of exposure dose to decommissioning workers and nearby residents is essential. Based on MARSSIM, a widely used decommissioning guideline in the United States, derivation of the exposure dose and derived concentration guideline level (DCGL) is mandatory using the probabilistic analysis of the RESRAD code. Here, DCGL is the radionuclide-specific concentration that satisfies the site release criteria. By applying the priority 1 parameter, which has the greatest effect on the dose, the dose is derived through deterministic and probabilistic analyses. The results were compared and analyzed. The purpose of this study was to provide a basic database that can be applied to the development of parameter lists and distributions suitable for the characteristics of nuclear facilities in South Korea. In addition, the process of deriving the dose by applying the deterministic and probabilistic analyses of RESRAD was assessed.

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