- 영문명
- 발행기관
- 한국방사성폐기물학회
- 저자명
- Donghee Lee Sunghwan Chung Yongdeog Kim Taehyung Na
- 간행물 정보
- 『Journal of Nuclear Fuel Cycle and Waste Technology (JNFCWT)』Vol.21 No.4, 531~541쪽, 전체 11쪽
- 주제분류
- 공학 > 공학일반
- 파일형태
- 발행일자
- 2023.12.30
4,120원
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국문 초록
The Wolsong Nuclear Power Plant (NPP) operates an on-site spent fuel dry storage facility using concrete silo and vertical module systems. This facility must be safely maintained until the spent nuclear fuel (SNF) is transferred to an external interim or final disposal facility, aligning with national policies on spent nuclear fuel management. The concrete silo system, operational since 1992, requires an aging management review for its long-term operation and potential license renewal. This involves comparing aging management programs of different dry storage systems against the U.S. NRC’s guidelines for license renewal of spent nuclear fuel dry storage facilities and the U.S. DOE’s program for long-term storage. Based on this comparison, a specific aging management program for the silo system was developed. Furthermore, the facility’s current practices—periodic checks of surface dose rate, contamination, weld integrity, leakage, surface and groundwater, cumulative dose, and concrete structure—were evaluated for their suitability in managing the silo system’s aging. Based on this review, several improvements were proposed.
영문 초록
목차
해당간행물 수록 논문
- Design and Structural Safety Evaluation of Transfer Cask for Dry Storage System of PWR Spent Nuclear Fuel
- Design and Structural Safety Evaluation of Canister for Dry Storage System of PWR Spent Nuclear Fuels
- Assessing the Potential of Small Modular Reactors (SMRs) in Spent Nuclear Fuel Management: A Review of the Generation IV Reactor Progress
- Numerical Modelling of Radionuclide Migration for the Underground Silo at Near-Field
- Thermal Analyses of Deep Geological Disposal Cell With Heterogeneous Modeling of PLUS7 Spent Nuclear Fuel
- Review of Aging Management for Concrete Silo Dry Storage Systems
- Preliminary Selection of Safety-Relevant Radionuclides for Long-Term Safety Assessment of Deep Geological Disposal of Spent Nuclear Fuel in South Korea
- Development of a Methodology for Estimating Radioactivity Concentration of NORM Scale in Scrap Pipes Based on MCNP Simulation
- Comparison of Environmental Radiation Survey Analysis Results in a High Dose Rate Environment Using CZT, NaI(Tl), and LaBr3(Ce) Detectors
- Characterization of the Purified Ca-type Bentonil-WRK Montmorillonite and Its Sorption Thermodynamics With Cs(I) and Sr(II)
- Rolling Test Simulation of Sea Transport of Spent Nuclear Fuel Under Normal Transport Conditions
- The French Underground Research Laboratory in Bure: An Essential Tool for the Development and Preparation of the French Deep Geological Disposal Facility Cigéo
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