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사용후핵연료 건식저장시스템 작업절차 및 작업형태 분석

Analysis of Spent Fuel Dry Storage System Work Procedures and Work Patterns

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초록

The Second High Level Radioactive Waste Management Basic Plan for Dry Interim Storage andInterim Storage of Spent Nuclear Fuel has been released. The Dual Purpose Canister (DPC) has emerged as away to avoid repeating the mistakes made by leading countries in spent fuel management by not considering thelinkages between management steps. From the worker’s point of view, the dose is likely to be influenced by theoperating procedures and work patterns of the dry storage facility. It is necessary to conduct a survey on the operatingprocedures and work patterns of each dry storage method before evaluating the exposure dose. The purpose of thisstudy is to investigate and analyze the work procedures and work patterns of commercially available DPC-basedspent fuel dry storage facilities in other countries. For this purpose, the dry storage systems commercialized overseaswere first categorized into 1) concrete overpack, 2) vertical storage module, and 3) metal overpack. The HI-STORM100, NAC-UMS, VSC-24, and Fuel Solutions systems were selected as the subjects of the study for the concreteoverpack method. The HI-STORM UMAX system was selected for the vertical storage module method, and theHI-STAR 100 system was selected for the metal overpack method. To analyze the operating procedures and workpatterns, the loading and unloading procedures described in the Final Safety Analysis Report (FSAR) for each systemwere analyzed, as well as the time and personnel required for each task. The results showed that, on average, theloading procedure requires 13.4 more steps and 644.5 more minute than the unloading procedure, although there aredetailed differences in operating procedures and work patterns among dry storage systems. The results of this studycan be used as a basis for the radiological impact assessment of workers during the operation of spent fuel dry storagefacilities.

Abstract

The Second High Level Radioactive Waste Management Basic Plan for Dry Interim Storage andInterim Storage of Spent Nuclear Fuel has been released. The Dual Purpose Canister (DPC) has emerged as away to avoid repeating the mistakes made by leading countries in spent fuel management by not considering thelinkages between management steps. From the worker’s point of view, the dose is likely to be influenced by theoperating procedures and work patterns of the dry storage facility. It is necessary to conduct a survey on the operatingprocedures and work patterns of each dry storage method before evaluating the exposure dose. The purpose of thisstudy is to investigate and analyze the work procedures and work patterns of commercially available DPC-basedspent fuel dry storage facilities in other countries. For this purpose, the dry storage systems commercialized overseaswere first categorized into 1) concrete overpack, 2) vertical storage module, and 3) metal overpack. The HI-STORM100, NAC-UMS, VSC-24, and Fuel Solutions systems were selected as the subjects of the study for the concreteoverpack method. The HI-STORM UMAX system was selected for the vertical storage module method, and theHI-STAR 100 system was selected for the metal overpack method. To analyze the operating procedures and workpatterns, the loading and unloading procedures described in the Final Safety Analysis Report (FSAR) for each systemwere analyzed, as well as the time and personnel required for each task. The results showed that, on average, theloading procedure requires 13.4 more steps and 644.5 more minute than the unloading procedure, although there aredetailed differences in operating procedures and work patterns among dry storage systems. The results of this studycan be used as a basis for the radiological impact assessment of workers during the operation of spent fuel dry storagefacilities.

참고문헌 (24)

  1. 2nd High Level Radioactive Waste Management Basic Plan, "MOTIE", ~ (2021)
  2. Time and Dose Assessment of Barge Shipment and At-Reactor Handling of a CASTOR V, "21 Spent Fuel Storage Cask", PNNL, 1992
  3. North Anna Power Station Units 1 & 2 Independent Spent Fuel Storage Installation(ISFSI)Safety Analysis Report, "North Anna Power Station", ~ (2016)
  4. Philippe FW, "Worker Exposure for At-Reactor Management of Spent Nuclear Fuel", Radiation Protection Dosimetry, 156(3), pp.386~393 (2013)[DOI]
  5. Design of Spent Fuel Storage Fuel Storage Facilities, "IAEA", ~, pp.Safety Series No.116 (1994)
  6. NRC, "Regulatory Guide 3.61, Standard Format and Content for a Topical Safety Analysis Report for a Spent Fuel Dry Storage Cask", ~ (1989)
  7. The state of the art of the Independent Spent Fuel Storage Installation in the USA, "KAERI", ~ (2010)
  8. Final Safety Analysis Report on the HISTORM 100 Cask System, "Holtec International", ~ (2016)
  9. Three Dimensional Thermal-Hydraulic Analyses for Diablo Canyon Site-Specific HI-STORM System Design, "Holtec International", ~ (2011)
  10. Indian Point Dry Cask Loadings and NRC’s ISFSI Oversight, "Dave Lochbaum", ~ (2023)
  11. Final Safety Analysis Report for the UMS Universal Storage System, "NAC International", ~ (2016)
  12. Maine Yankee Independent Spent Fuel Storage Installation, "Maine Yankee Atomic Power Company", ~ (2019)
  13. Palo Verde Nuclear Generating Station Units 1, 2 and 3 and Independent Spent Fuel Storage Installation, "Arizona Public Service Company", ~ (2024)
  14. Final Safety Analysis Report for the VSC-24 Ventilated Storage Cask System, "BNG Fuel Solutions", ~ (2005)
  15. VSC-24 Ventilated Storage Cask Certificate of Compliance Renewal Application, "Energy Solutions", ~ (2012)
  16. Fuel Solutions Storage System Final Safety Analysis Report, "Enery Solutions", ~ (2007)
  17. ISFSI Decommissioning Funding Plans, "Entergy Nuclear Operations", ~ (2021)
  18. Final Safety Analysis Report on the HISTORM UMAX Canister Storage System, "Holtec International", ~ (2016)
  19. San Onofre Nuclear Generation Station Units 1, 2 and 3 And Independent Spent Fuel Storage Facility, "Southern California Edison", ~ (2020)
  20. Ameren Missouri, "Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0036", ~ (2018)
  21. Final Safety Analysis Report on the HISTAR 100 MPC Storage System, "Holtec International", ~ (2020)
  22. Analysis and design of dry cask storage pads for plant hatch ISFSI, "IAEA", ~ (2001)
  23. Present Status for Dry Storage of Spent Nuclear Fuel, "KAERI", ~ (2003)
  24. Final Safety Analysis Report on the HISTORM FW Cask System, "Holtec International", ~ (2012)

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