논문 상세보기

Selection of Safety Information for the Delivery of PWR Spent Nuclear Fuel

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한국방사성폐기물학회 학술논문요약집 (Abstracts of Proceedings of the Korean Radioactive Wasts Society)
한국방사성폐기물학회 (Korean Radioactive Waste Society)
초록

The manufactured nuclear fuel assembly is loaded into the nuclear reactor after the core design, and is finally discharged to the wet storage pool after depletion for 3 cycles. The discharged spent nuclear fuel is transported and stored in a dry storage system at the on-site of the nuclear power plant, which is cooled by natural convection, and undergoes final disposal or reprocessing through an intermediate dry storage facility. In this series of processes, the characteristics of the final product, the spent fuel, vary depending on the environmental conditions, so it is essential to manage each history data to verify the long-term integrity of the spent nuclear fuel. In this paper, safety information on spent nuclear fuel is described in order to establish technical requirements that should be considered in each stage of storage, transport, reprocessing, and disposal of spent nuclear fuel. Comprehensive safety information on spent nuclear fuel is basically calculated from basic information that considers characteristic information that can be obtained through the manufacture and design of nuclear fuel assemblies, operation history in a nuclear reactor, and location history in a wet storage pool. It can be divided into secondary production information (SF Burnup, Nuclide Inventory, etc.) and tertiary integrity-related information obtained through cladding inspection during spent fuel storage. KHNP produces this multi-layered information according to the production stage and manages it through the comprehensive management system of the spent nuclear fuel, and safety information with some errors is not only improved through re-verification but also continuously updated. In this paper, the spent nuclear fuel safety information was derived based on various information calculated in the entire process of being discharged and managed in a wet storage pool, including new fuel manufacturing information and depletion history. Such safety information will be used as basic data for long-term safe management of spent nuclear fuel, and will be continuously produced and managed. In the future, additional discussions will be held on the safety information of the spent nuclear fuel through consultation with KORAD and regulatory agencies.

저자
  • Kiyoung Kim(Central Research Institute, Korea Hydro & Nuclear Power Company Limited, 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon) Corresponding author
  • Donghee Lee(Central Research Institute, Korea Hydro & Nuclear Power Company Limited, 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon)
  • Yongdeog Kim(Central Research Institute, Korea Hydro & Nuclear Power Company Limited, 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon)
  • Jongho Hong(Korea Hydro & Nuclear Power Company Limited, 1655, Bulguk-ro, Munmudaewang-myeon, Gyeongju-si, Gyeongsangbuk-do)