Thermal Safety Evaluation of Buffer for Preliminary Conceptual Design of SNF Disposal System
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초록
The conceptual design of the spent nuclear fuel (SNF) disposal system is significantin that it must maintain the safety for a very long period in consideration of geologicalcharacteristics. A buffer, one of the important components of the SNF disposal system, minimizesthe inflow of groundwater and relieves the shock caused by a mechanical factor. In order toconstruct an optimal disposal system, as decay heat of SNF causes temperature variation inthe buffer that affects the mechanical performance of the system, it is substantial to estimateaccurately the temperature variation. Therefore, in this study, the disposal environment requiredfor thermal evaluation of buffer was established by reflecting domestic conditions. Usingthis setting value, the thermal evaluation of buffer was performed according to the distancebetween disposal pits and the change of overpack material in the disposal cask. As a result of theevaluation, it was confirmed that most of the cases had satisfied the criteria of thermal safety, butsome of the cases had not.
Abstract
The conceptual design of the spent nuclear fuel (SNF) disposal system is significantin that it must maintain the safety for a very long period in consideration of geologicalcharacteristics. A buffer, one of the important components of the SNF disposal system, minimizesthe inflow of groundwater and relieves the shock caused by a mechanical factor. In order toconstruct an optimal disposal system, as decay heat of SNF causes temperature variation inthe buffer that affects the mechanical performance of the system, it is substantial to estimateaccurately the temperature variation. Therefore, in this study, the disposal environment requiredfor thermal evaluation of buffer was established by reflecting domestic conditions. Usingthis setting value, the thermal evaluation of buffer was performed according to the distancebetween disposal pits and the change of overpack material in the disposal cask. As a result of theevaluation, it was confirmed that most of the cases had satisfied the criteria of thermal safety, butsome of the cases had not.
참고문헌 (20)
- User’s Manual, "ABAQUS Standard", pp.2018, ABAQUS
- Baumgartner P, "Technical Implication of Aging Used Fuel Prior to Disposal Within a Deep Geologic Repository. Canadian Nuclear Society, Waste Management, Decommissioning and Environmental Restoration for Canada’s Nuclear Activities: Current Practice and Future Needs", ~ (2005)
- 조동건, "파이로공정 시설 개념설계를 위한 기준 사용후핵연료 선정", Journal of Nuclear Fuel Cycle and Waste Technology, 6(3), pp.225~232 (2008), 한국방사성폐기물학회
- Cho KD, "Characteristics of a Geological Disposal System for the Increasing Burn-up of Spent Nuclear Fuel in Korea", J. Nucl. Sci. Technol, 44, pp.1306~1316 (2007)
- 최희주, "한국형 기준 처분환경에서의 PWR 사용후핵연료 처분용기의 구조적 안전성 해석", Journal of Nuclear Fuel Cycle and Waste Technology, 4(3), pp.301~309 (2006), 한국방사성폐기물학회
- Task Order 18: Generic Design for Small Standardized Transportation. Aging and Disposal Canister Systems - Updated Final Report, "Energysolutions", ~ (2015)
- H12 Project to Establish Technical Basis for HLW disposal in Japan. Supporting Report 2 - Repository Design & Engineering Technology, "Japan Nuclear Cycle Development Institute", ~ (1999)
- Thermal Analyses of Spent Fuel Nuclear Fuel Repository, "Kari I", ~, pp.POSIVA 2003-04 (2003)
- 김민준, "벤토나이트 완충재의 열물성이 온도 변화에 미치는 영향", 한국지반공학회논문집, 34(1), pp.17~24 (2018), 한국지반공학회[DOI]
- Reference Spent Fuel and Its Source Terms for a Design of Deep Geological Disposal System, "Korea Atomic Energy Research Institute", ~, pp.KAERI (2005), TR-3084
- Korean Reference HLW Disposal System, "Korea Atomic Energy Research Institute", Korea Atomic Energy Research Institute, 23~35, pp.KAERI (2008), TR-3563[DOI]
- Final Report of EBS Development for Spent Fuel Disposal, "Korea Radioactive Waste Agency", ~, pp.TR2014-06 (2014)
- Report on the Status of Operation of HLW Management Facilities in Foreign Countries, "Korea Radioactive Waste Agency", ~ (2018)
- Lee JY, "Concept of a Korean Reference Disposal System for Spent Fuels", J. Nucl. Sci. Technol, 44, pp.1565~1573 (2007)
- Lee JY, "Analyses of Disposal Efficiency Based on Nuclear Spent Fuel Cooling Time and Disposal Tunnel", pit for the Design of a Geological Repository, 2011, pp.53, 361~367
- Preliminary Conceptual Design of the Korean Reference Repository System for HLW in Vertical Emplacement, "Lee JY", Korea Atomic Energy Research Institute Technical, ~, pp.KAERI (2005), TR-3012[DOI]
- Modelling of Buffer Material Behavior. Some Examples of Material Models and Performance Calculations, "Lennart B", SKB, ~ (1988)
- Malbrain CM, "Analytical Approximations for the Long Term Decay Behavior of spent Fuel and High-level Waste", Nucl. Technol, 57, pp.292~305 (1982)
- Okmark H, "Use of an Analytical Solution for Calculating Temperatures in Repository Host Rack", Engineering Geology (2005)
- Sander E, "Review of the Development of the Transportation, Aging, and Disposal (TAD) Waste Disposal System for the Proposed Yucca Mountain Geologic Repository", Prog. Nucl. Energy, 62, pp.8~15 (2013)