Journal of Radiation Industry (방사선산업학회지)

Korean Society of Radiation Industry (한국방사선산업학회)
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Preliminary Radiation Exposure Dose Evaluation for Workers of the Landfill Disposal Facility Considering the Radiological Characteristics of Very Low Level Concrete and Metal Decommissioning Wastes

극저준위 콘크리트, 금속 해체방폐물의 방사선적 특성을 고려한 매립형 처분시설 방사선작업자 예비 피폭선량 평가

  • Ho-Seog Dho (Korea Radioactive Waste Agency) ;
  • Ye-Seul Cho (Korea Radioactive Waste Agency) ;
  • Hyun-Goo Kang (Korea Radioactive Waste Agency) ;
  • Jae-Chul Ha (Korea Radioactive Waste Agency)
  • 도호석 (한국원자력환경공단) ;
  • 조예슬 (한국원자력환경공단) ;
  • 강현구 (한국원자력환경공단) ;
  • 하재철 (한국원자력환경공단)
  • Received : 2023.10.16
  • Accepted : 2023.11.10
  • Published : 2023.12.31
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Abstract

The Kori Unit 1 nuclear power plant, which is planned to be dismantled after permanent shutdown, is expected to generate a large amount of various types of radioactive waste during the dismantling process. For the disposal of Very-low-level waste, which is expected to account for the largest amount of generation, the Korea Radioactive waste Agency (KORAD) is in the process of detailed design to build a 3-phase landfill disposal facility in Gyeongju. In addition, a large container is being developed to efficiently dispose of metal and concrete waste, which are mainly generated as Very low-level waste of decommissioning. In this study, based on the design characteristics of the 3-phase landfill disposal facility and the large container under development, radiation exposure dose evaluation was performed considering the normal and accident scenarios of radiation workers during operation. The direct exposure dose evaluation of workers during normal operation was performed using the MCNP computer program, and the internal and external exposure dose evaluation due to damage to the decommissioning waste package during a drop accident was performed based on the evaluation method of ICRP. For the assumed scenario, the exposure dose of worker was calculated to determine whether the exposure dose standards in the domestic nuclear safety act were satisfied. As a result of the evaluation, it was confirmed that the result was quite low, and the result that satisfied the standard limit was confirmed, and the radiational disposal suitability for the 3-phase landfill disposal facility of the large container for dismantled radioactive waste, which is currently under development, was confirmed.

Keywords

Acknowledgement

본 논문은 에너지기술평가원(KETEP)에서 주관하는 원자력핵심기술개발 "방사성폐기물 종류별 물리적 특성 규명을 통한 처분시설 폐쇄 후 안전성 평가 체계 고도화" 과제(과제번호 : RS-2023-00235182)의 일환으로 수행되었습니다.

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