Journal of Radiation Industry (방사선산업학회지)

Korean Society of Radiation Industry (한국방사선산업학회)
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Preliminary Design Evaluation of Auxiliary Equipment for Transportation and Storage of Multi-purpose Canister

사용후핵연료 다목적 캐니스터의 운반 및 저장 보조 설비에 대한 예비설계 평가

  • 신창민 (한국원자력환경공단 고준위기술개발원) ;
  • 이상환 (한국원자력환경공단 고준위기술개발원) ;
  • 이연오 ((주)세아베스틸) ;
  • 정인수 ((주)코네스코퍼레이션 기술연구소) ;
  • 차길용 (주)래드코어)
  • Received : 2023.08.25
  • Accepted : 2023.09.21
  • Published : 2023.09.30
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Abstract

A multi-purpose canister (MPC) was developed for the purpose of transportation, storage and disposal of spent nuclear fuel (SNF) and has the advantage of minimizing repackaging between management stages of SNF. Considering the typical rock characteristics in Korea, a disposal canister is expected to contain 4 assemblies of Pressurized water reactor (PWR) SNF. The capacity of the MPC should be similarly designed with the disposal canister. However, the MPC with four SNF assemblies is expected to be less efficient in transporting and storing compared to a large-capacity canister. Therefore, a preliminary concept was derived for an auxiliary equipment that can transport and store multiple MPCs in a large overpack. A previously derived concept from US was thoroughly reviewed, and the preliminary concept was revised considering domestic situations including crane capacity and others. In addition, the safety of the normal transportation and storage of the MPC placed in transportation and storage overpack was evaluated with the auxiliary equipment.

Keywords

Acknowledgement

본 연구는 산업통상자원부 에너지기술평가원 기술개발과제(No. 20211710200010B)의 연구비를 지원받아 수행되었습니다.

References

  1. Heikki R and Jukka-Pekka S. 1996. Design report of the canister for nuclear fuel disposal, POSIVA-96-13. 
  2. Energy Solutions. 2013. Task Order 12: Standardized Transportation, Aging and Disposal Canister Feasibility Study. 
  3. US DOE. 1997. Topical Report on Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages, Rev.1. 
  4. ORNL. 2011. Scale: A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design, ORNL/TM-2005/39 Version 6.1. 
  5. NSSC Rule No. 29. 2021. The Rule on Technical Standards for Radiation Safety Management. 
  6. Pelowitz DB. 2013. MCNP6 USER'S MANUAL (Version1.0) LA-CP-13-00634 Rev.0. 
  7. ICRP. 1996. Conversion Coefficients for use in Radiological Protection against External Radiation, ICRP Publication 74. 
  8. DASSAULT SIMULIA, ABAQUS. 2017. 
  9. American Society of Mechanical Engineers. 2019. ASME Boiler and Pressure Vessel Code, Section II, Part A-Ferrous Material Specifications, 2019 Edition. 
  10. American Society of Mechanical Engineers. 2019. ASME Boiler and Pressure Vessel Code, Section II, Part D-Properties, 2019 Edition. 
  11. NSSC Notice 2021-02. 2021. The Regulation on the packaging and transportation of radioactive materials. 
  12. IAEA Safety Standards No. SSR-6. 2012. Regulations for the Safe Transport of Radioactive Material, International Atomic Energy Agency, 2012 Edition. 
  13. Title 10, Code of Federal Regulations Part 71 (10CFR71). 2012. Packaging and Transportation of Radioactive Material. 
  14. US Nuclear Regulatory Commission. 1978. Regulatory Guide 7.6, Design Criteria for the Structural Analysis of Shipping Cask Containment Vessels. 
  15. US Nuclear Regulatory Commission. 1989. Regulatory Guide 7.8, Load Combinations for the Structural Analysis of Shipping Casks for Radioactive Material. 
  16. US Nuclear Regulatory Commission. 2020. NUREG-2215, Standard Review Plan for Spent Fuel Dry Storage Systems and Facility. 
  17. Title 10 of the Code of Federal Regulations. 2012. Part 72. Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Wast, and Reactor Related Greater than Class C Waste. 
  18. Korea Electric Association. 2015. KEPIC STA, Design Load. 
  19. CMAA#70. 1998. Specifications for Electric Overhead Traveling Cranes, Crane Manufacturers Association of America. 
  20. ANSI-N14.6. 1993. Special Lifting Devices for Shipping Containers Weighing 10,000 Pounds or More. 
  21. American Society of Mechanical Engineers (ASME). 2019. Boiler and Pressure Vessel Code, Section III, Division 3, Containments for Transportation and Storage for Spent Nuclear Fuel and High Level Radioactive Material and Waste, 2019 Edition. 
  22. American Society of Mechanical Engineers. 2019. ASME Code, Section III, Division 1, Subsection NB, 2019 Edition. 
  23. American Society of Mechanical Engineers (ASME). 2019. Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NG, Core Support Structures, 2019 Edition. 
  24. American Society of Mechanical Engineers (ASME). 2019. Boiler and Pressure Vessel Code, Section III, Division 1, Appendix F, Rules for Evaluation of Service Loadings with Level D Service Limits, 2019 Edition.