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건식 저장방식별 사용후핵연료 운반 작업자 피폭시나리오 개발

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

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Currently, there are no interim storage facilities and permanent disposal facilities in Korea, so all spentnuclear fuels are temporarily stored. However, the temporary storage facility is approaching saturation, and as a measureto this, the 2nd Basic Plan for the Management of High-Level Radioactive Waste presented an operation plan fordry interim storage facilities and dry temporary storage facilities on the NPP on-site. The dry storage can be operatedin 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 andevaluate and compare the radiological impact for each method. The purpose of this study is to develop an exposurescenario for workers transporting spent nuclear fuel by dry storage method. To this end, first, the operation procedureof 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 storagemodule-based system were selected for analysis. Factors were assumed that could affect the type of work (workingdistance, working hours, number of workers, etc.) during transportation work. Finally, the work type of the processesinvolved in transporting spent nuclear fuel by dry storage method was set, and an exposure scenario was developedaccordingly. The concrete overpack method, the metal overpack method, and the vertical storage module methodwere classified into a total of 31, 9, and 23 processes, respectively. The work distance, work time, and number ofworkers for each process were set. The product of working hours and number of workers (Man-hour) was set high inthe order of concrete overpack method, vertical storage module method, and metal overpack method, and short-rangework (10 cm) was most often applied to the concrete overpack method. The results of this study are expected to beused as basic data for performing radiological comparisons of transport workers by dry storage method of spent nuclearfuel.

Abstract

Currently, there are no interim storage facilities and permanent disposal facilities in Korea, so all spentnuclear fuels are temporarily stored. However, the temporary storage facility is approaching saturation, and as a measureto this, the 2nd Basic Plan for the Management of High-Level Radioactive Waste presented an operation plan fordry interim storage facilities and dry temporary storage facilities on the NPP on-site. The dry storage can be operatedin 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 andevaluate and compare the radiological impact for each method. The purpose of this study is to develop an exposurescenario for workers transporting spent nuclear fuel by dry storage method. To this end, first, the operation procedureof 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 storagemodule-based system were selected for analysis. Factors were assumed that could affect the type of work (workingdistance, working hours, number of workers, etc.) during transportation work. Finally, the work type of the processesinvolved in transporting spent nuclear fuel by dry storage method was set, and an exposure scenario was developedaccordingly. The concrete overpack method, the metal overpack method, and the vertical storage module methodwere classified into a total of 31, 9, and 23 processes, respectively. The work distance, work time, and number ofworkers for each process were set. The product of working hours and number of workers (Man-hour) was set high inthe order of concrete overpack method, vertical storage module method, and metal overpack method, and short-rangework (10 cm) was most often applied to the concrete overpack method. The results of this study are expected to beused as basic data for performing radiological comparisons of transport workers by dry storage method of spent nuclearfuel.

참고문헌 (24)

  1. NEA, "Storage of Radioactive Waste and Spent Fuel", ~ (2020)
  2. KORAD, "Story about Spent Nuclear Fuel 70", ~ (2016)
  3. "Spent Nuclear Fuel Management Process"[URL]
  4. Korean 2nd Basic Plan for the Management of HLW, "MOTIE", ~ (2021)
  5. "Code of Federal Regulations, Part 73-Physical Protection of Plants and Materials; 10 CFR 72", ~
  6. Standard Review Plan for Spent Fuel Dry Storage Systems at a General License Facility-Final Report, "NRC", ~, pp.NUREG-1536 (2010)
  7. Final Safety Analysis Report on the HISTAR 100 MPC Storage System, "Holtec International", ~ (2020)
  8. Final Safety Analysis Report on the HISTORM FW Cask System, "Holtec International", ~ (2012)
  9. Final Safety Analysis Report on the HISTORM UMAX Canister Storage System, "Holtec International", ~ (2016)
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  11. Safety Analysis Report on the HI-STORE CIS, "Holtec International", ~ (2017)
  12. Final Safety Analysis Report for the VSC-24 Ventilated Storage Cask System, "BNG Fuel Solutions", ~ (2005)
  13. Fuel Solutions Storage System Final Safety Analysis Report, "EnerySolutions", ~ (2007)
  14. Final Safety Analysis Report for the UMS Universal Storage System, "NAC International", ~ (2016)
  15. Time and Dose Assessment of Barge Shipment and At-Reactor Handling of a CASTOR V, "21 Spent Fuel Storage Cask", PNNL, 1992
  16. Philippe FW, "Worker Exposure for At-Reactor Management of Spent Nuclear Fuel", Radiation Protection Dosimetry, 156(3), pp.386~393 (2013)[DOI]
  17. Kim TM, "Preliminary Assessment of Radiation Impact from Dry Storage Facilities for PWR Spent Fuel", Journal of Radiation Protection, 37(4), pp.197~201 (2012)[DOI]
  18. Kim TM, "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), pp.391~402 (2017)[DOI]
  19. Dho HS, "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), pp.351~352 (2015)[DOI]
  20. "Code of Federal Regulations, Part 104-Physical Protection of Plants and Materials; 10 CFR 72", ~
  21. NSSC, "Nuclear Safety Act Article 91", ~ (2024)
  22. NSSC, "Enforcement Decree of the Nuclear Safety Act Article 134", ~ (2023)
  23. Kim TH, "Conceptual Design, Development, and Preliminary Safety Evaluation of a PWR Dry Storage Module for Spent Nuclear Fuel", Applied Sciences, 12(9), pp.4587~ (2022)[DOI]
  24. Chung SH, "On-site Transport and Storage of Spent Nuclear Fuel at Kori NPP by KN-12 Transport Cask", Journal of the Korean Radioactive Waste Society, 4(1), pp.51~58 (2006)

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