Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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External exposure specific analysis for radiation worker in reuse of containment building for Kori Unit 1

  • Byon, Jihyang (School of Mechanical Engineering, Pusan National University) ;
  • Park, Sangjune (School of Mechanical Engineering, Pusan National University) ;
  • Kim, Yangjin (School of Mechanical Engineering, Pusan National University) ;
  • Ahn, Seokyoung (School of Mechanical Engineering, Pusan National University)
  • Received : 2021.04.09
  • Accepted : 2021.11.15
  • Published : 2022.05.25
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Abstract

The containment building Kori Unit 1 may require sequential steps for full decommissioning. This study assumes that the containment building is to be used as an auxiliary building that handles nuclear power systems and materials during decommissioning before conversion into a greenfield. Through the derivation of guidelines and dose evaluation, it was confirmed whether the radiation workers were satisfied with the ALARA decision. The specific modeling of the external radiation exposure was performed based on the facility investigation procedures. The external radiation specific derived concentration guideline levels (DCGLs) for radiation workers in containment building were obtained using the RESRAD-BUILD code and were applied to the VISIPLAN 3D ALARA Planning Tool code to calculate the working dose and check worker safety. The derivation of site-specific and realistic DCGLs and dose evaluation via 3D modeling can contribute to the scenario development for the decommission and remediation of containment building.

Keywords

Acknowledgement

This work was supported by a National Research Foundation of Korea grant provided by the Korean government [No. NRF-2018M2B2B1065637] and the Nuclear Safety Research Program through the Korea Foundation of Nuclear Safety (KoFONS) using the financial resource granted by the Nuclear Safety and Security Commission (NSSC) (No.2106026).

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