방사선산업학회지 (Journal of Radiation Industry)

한국방사선산업학회 (Korean Society of Radiation Industry)
권호 표지
DOI QR코드

DOI QR Code

건식 저장방식별 사용후핵연료 운반 작업자 피폭시나리오 개발

Development of Spent Nuclear Fuel Transportation Worker Exposure Scenario by Dry Storage Methods

  • 손건우 (경희대학교 원자력공학과) ;
  • 김혁재 (경희대학교 원자력공학과) ;
  • 이신동 (경희대학교 원자력공학과) ;
  • 곽민우 (경희대학교 원자력공학과) ;
  • 김광표 (경희대학교 원자력공학과)
  • Geon Woo Son (Department of Nuclear Engineering, Kyung Hee University) ;
  • Hyeok Jae Kim (Department of Nuclear Engineering, Kyung Hee University) ;
  • Shin Dong Lee (Department of Nuclear Engineering, Kyung Hee University) ;
  • Min Woo Kwak (Department of Nuclear Engineering, Kyung Hee University) ;
  • Kwang Pyo Kim (Department of Nuclear Engineering, Kyung Hee University)
  • 투고 : 2024.03.07
  • 심사 : 2024.03.25
  • 발행 : 2024.03.31
PDF 다운로드
⟨ 이전 논문 다음 논문 ⟩

초록

Currently, there are no interim storage facilities and permanent disposal facilities in Korea, so all spent nuclear fuels are temporarily stored. However, the temporary storage facility is approaching saturation, and as a measure to this, the 2nd Basic Plan for the Management of High-Level Radioactive Waste presented an operation plan for dry interim storage facilities and dry temporary storage facilities on the NPP on-site. The dry storage can be operated in various ways, and to select the optimal dry storage method, the reduction of exposure for workers must be considered. Accordingly, it is necessary to develop a worker exposure scenario according to the dry storage method and evaluate and compare the radiological impact for each method. The purpose of this study is to develop an exposure scenario for workers transporting spent nuclear fuel by dry storage method. To this end, first, the operation procedure of the foreign commercial spent nuclear fuel dry storage system was analyzed based on the Final Safety Analysis Report (FSAR). 1) the concrete overpack-based system, 2) the metal overpack-based system, and 3) the vertical storage module-based system were selected for analysis. Factors were assumed that could affect the type of work (working distance, working hours, number of workers, etc.) during transportation work. Finally, the work type of the processes involved in transporting spent nuclear fuel by dry storage method was set, and an exposure scenario was developed accordingly. The concrete overpack method, the metal overpack method, and the vertical storage module method were classified into a total of 31, 9, and 23 processes, respectively. The work distance, work time, and number of workers for each process were set. The product of working hours and number of workers (Man-hour) was set high in the order of concrete overpack method, vertical storage module method, and metal overpack method, and short-range work (10 cm) was most often applied to the concrete overpack method. The results of this study are expected to be used as basic data for performing radiological comparisons of transport workers by dry storage method of spent nuclear fuel.

키워드

과제정보

본 연구는 한국에너지기술평가원에서 주관하는 에너지 기술개발사업의 일환으로 수행된 연구입니다(No. 2021171020001B).

참고문헌

  1. NEA. 2020. Storage of Radioactive Waste and Spent Fuel.
  2. KORAD. 2016. Story about Spent Nuclear Fuel 70.
  3. KHNP. Spent Nuclear Fuel Management Process. https://npp.khnp.co.kr/index.khnp?menuCd=DOM_000000103004001000
  4. MOTIE. 2021. Korean 2nd Basic Plan for the Management of HLW.
  5. Code of Federal Regulations, Part 73-Physical Protection of Plants and Materials; 10 CFR 72.
  6. NRC. 2010. Standard Review Plan for Spent Fuel Dry Storage Systems at a General License Facility-Final Report. NUREG-1536.
  7. Holtec International. 2020. Final Safety Analysis Report on the HI-STAR 100 MPC Storage System.
  8. Holtec International. 2012. Final Safety Analysis Report on the HI-STORM FW Cask System.
  9. Holtec International. 2016. Final Safety Analysis Report on the HI-STORM UMAX Canister Storage System.
  10. Holtec International. 2016. Final Safety Analysis Report on the HI-STORM 100 Cask System.
  11. Holtec International. 2017. Safety Analysis Report on the HI-STORE CIS.
  12. BNG Fuel Solutions. 2005. Final Safety Analysis Report for the VSC-24 Ventilated Storage Cask System.
  13. EnerySolutions. 2007. Fuel Solutions Storage System Final Safety Analysis Report.
  14. NAC International. 2016. Final Safety Analysis Report for the UMS Universal Storage System.
  15. PNNL. 1992. Time and Dose Assessment of Barge Shipment and At-Reactor Handling of a CASTOR V/21 Spent Fuel Storage
  16. Philippe FW. 2013. Worker Exposure for At-Reactor Management of Spent Nuclear Fuel. Radiation Protection Dosimetry 156(3):386-393. https://doi.org/10.1093/rpd/nct083
  17. Kim TM, Baeg CY, Cha GY, Lee WG, Kim SY. 2012. Preliminary Assessment of Radiation Impact from Dry Storage Facilities for PWR Spent Fuel. Journal of Radiation Protection 37(4):197-201. https://doi.org/10.14407/jrp.2012.37.4.197
  18. Kim TM, Dho HS, Cho CH, Ko JH. 2017. Preliminary Shielding Analysis of the Concrete Cask for Spent Nuclear Fuel Under Dry Storage Conditions. Journal of Nuclear Fuel Cycle and Waste Technology 15(4):391-402. https://doi.org/10.7733/jnfcwt.2017.15.4.391
  19. Dho HS, Kim TM, Cho, CH. 2015. Shielding Analysis for the Design of Temporary Shield for Spent Nuclear Fuel Metal Storage Cask. Journal of Nuclear Fuel Cycle and Waste Technology 13(2):351-352. https://doi.org/10.7733/jnfcwt.2016.14.4.411
  20. Code of Federal Regulations, Part 104-Physical Protection of Plants and Materials; 10 CFR 72.
  21. NSSC. 2024. Nuclear Safety Act Article 91.
  22. NSSC. 2023. Enforcement Decree of the Nuclear Safety Act Article 134.
  23. Kim TH, Kim KY, Lee DH, Na TH, Chung SH, Kim YD. 2022. Conceptual Design, Development, and Preliminary Safety Evaluation of a PWR Dry Storage Module for Spent Nuclear Fuel. Applied Sciences 12(9):4587. https://doi.org/10.3390/app12094587
  24. Chung SH, Baeg CY, Choi BI, Yang KH, Lee DK. 2006. On-site Transport and Storage of Spent Nuclear Fuel at Kori NPP by KN12 Transport Cask. Journal of the Korean Radioactive Waste Society 4(1):51-58.