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Evaluation of Functional Capability for Spent Fuel Drops in PWR Spent Fuel Rack KCI 등재 SCOPUS

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방사성폐기물학회지 (Journal of the Korean Radioactive Waste Society)
한국방사성폐기물학회 (Korean Radioactive Waste Society)
초록

The spent nuclear fuel, combusted and released in the nuclear power plant, is stored in the spent fuel pool (SFP) located in the fuel buildings interconnected with the reactors. In Korea, spent fuel has been stored exclusively in SFPs, prompting initiatives to expand storage capacity by either installing additional SFPs or replacing them with high-density spent fuel storage racks. The installation of these fuel racks necessitates obtaining a regulatory license contingent upon ensuring safe fuel handling and storage systems. Regulatory agencies mandate the formulation of various postulated accident scenarios and assessments covering criticality, shielding, thermal behavior, and structural integrity to ensure safe fuel handling and storage systems. This study describes an evaluation method for assessing the structural damage to storage racks resulting from fuel dropping as a part of the functional safety evaluation of these racks. A scenario was envisaged wherein fuel was dropped onto the base plates of the upper and lower sections of the storage racks, and the impact load was analyzed using the ABAQUS/Explicit program. The evaluation results revealed localized plastic deformation but affirmed the structural integrity and safety of the storage racks.

목차
1. Introduction
2. Dropping Accident of Spent Fuel
    2.1 Evaluation Conditions
    2.2 Shallow Drop
    2.3 Deep Drop-1
    2.4 Deep Drop-2
3. Criteria for Mechanical Accidents
4. Analysis of Accidents
    4.1 Assumptions
    4.2 Analysis Method
5. Analysis Results
    5.1 Shallow Drop
    5.2 Deep Drop-1
    5.3 Deep Drop-2
6. Conclusion
Conflict of Interest
Acknowledgements
REFERENCES
저자
  • Taehyung Na(Central Research Institute, Korea Hydro & Nuclear Power Co., Ltd., 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon 34101, Republic of Korea) Corresponding author
  • Donghee Lee(Central Research Institute, Korea Hydro & Nuclear Power Co., Ltd., 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon 34101, Republic of Korea)
  • Kyungho Roh(Central Research Institute, Korea Hydro & Nuclear Power Co., Ltd., 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon 34101, Republic of Korea)
  • Sunghwan Chung(Central Research Institute, Korea Hydro & Nuclear Power Co., Ltd., 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon 34101, Republic of Korea)