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사고 대응 작업자 피폭선량 평가

Dose Assessment for Workers in Accidents

  • 김준혁 (한국전력기술 원전기술연구소) ;
  • 윤선홍 (한국전력기술 원전기술연구소) ;
  • 차길용 (래드코어) ;
  • 배진형 (한국전력기술 원전기술연구소)
  • 투고 : 2023.08.10
  • 심사 : 2023.09.06
  • 발행 : 2023.09.30

초록

To effectively and safely manage the radiation exposure to nuclear power plant (NPP) workers in accidents, major overseas NPP operators such as the United States, Germany, and France have developed and applied realistic 3D model radiation dose assessment software for workers. Continuous research and development have recently been conducted, such as performing NPP accident management using 3D-VR based on As Low As Reasonably Achievable (ALARA) planning tool. In line with this global trend, it is also required to secure technology to manage radiation exposure of workers in Korea efficiently. Therefore, in this paper, it is described the application method and assessment results of radiation exposure scenarios for workers in response to accidents assessment technology, which is one of the fundamental technologies for constructing a realistic platform to be utilized for radiation exposure prediction, diagnosis, management, and training simulations following accidents. First, the post-accident sampling after the Loss of Coolant Accident(LOCA) was selected as the accident and response scenario, and the assessment area related to this work was established. Subsequently, the structures within the assessment area were modeled using MCNP, and the radiation source of the equipment was inputted. Based on this, the radiation dose distribution in the assessment area was assessed. Afterward, considering the three principles of external radiation protection (time, distance, and shielding) detailed work scenarios were developed by varying the number of workers, the presence or absence of a shield, and the location of the shield. The radiation exposure doses received by workers were compared and analyzed for each scenario, and based on the results, the optimal accident response scenario was derived. The results of this study plan to be utilized as a fundamental technology to ensure the safety of workers through simulations targeting various reactor types and accident response scenarios in the future. Furthermore, it is expected to secure the possibility of developing a data-based ALARA decision support system for predicting radiation exposure dose at NPP sites.

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과제정보

이 논문은 2023년도 정부(산업통상자원부)의 재원으로 한국에너지기술평가원의 지원을 받아 수행된 연구임(No. 20224B10300090, ALARA 분석평가 프로그램 및 3D-BIM 기반 실감몰입형 피폭선량 예측진단 통합시스템 기술개발).

참고문헌

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  2. Institute for Energy Technology Halden Virtual Reality Centre4., 20174., Software User Manual HVRC VRdose Planner User Guide. Issue 2 Revision 0.
  3. Los Alamos National Laboratory. 2018. A General Monte Carlo N Particale Transport Code, Version 6.2. LA-UR-18-20808, Rev.0.
  4. Oak Ridge National Laboratory. 2011. Scale: A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design. ORNL/TM-2005/39.
  5. ICRP. 1996. Conversion Coefficients for Use in Radiological Protection Against External Radiation. ICRP Publication 74.