처분시스템 설계를 위한 경수로 사용후핵연료 처분용기 열해석 평가
Thermal Analysis of PWR Spent Nuclear Fuel Disposal Canister for Disposal System: Canister Design and Disposal Concepts
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The thermal analyses of various disposal canisters using ANSYS Mechanical code were performedconsidering the vertical and horizontal disposal concepts. ACE7 Pressurized Water Reactor (PWR) type of SpentNuclear Fuel (SNF) was considered and 4 fuel assemblies in one disposal canister were used as the source term. In thevertical disposal concept, the KBS-3 and postulated type of disposal canisters showed that those peak temperatureswere lower than 100oC compared to STAD type of disposal canister. In the horizontal disposal concept, the peaktemperatures of KBS-3, Nagra and postulated type of disposal canisters were lower than 100oC, which satisfied thethermal design requirement of the disposal system. In this study, the higher peak temperature results of disposalcanisters indicated the greater thickness of bentonite buffer as the heat transfer effect get reduced. In addition, the heattransfer effect was also influenced by the distance between deposition hole and the dimension of disposal canisters. This study can be used for further research regarding Deep Geological Repository (DGR) design considering variousdisposal canisters and disposal concepts.
Abstract
The thermal analyses of various disposal canisters using ANSYS Mechanical code were performedconsidering the vertical and horizontal disposal concepts. ACE7 Pressurized Water Reactor (PWR) type of SpentNuclear Fuel (SNF) was considered and 4 fuel assemblies in one disposal canister were used as the source term. In thevertical disposal concept, the KBS-3 and postulated type of disposal canisters showed that those peak temperatureswere lower than 100oC compared to STAD type of disposal canister. In the horizontal disposal concept, the peaktemperatures of KBS-3, Nagra and postulated type of disposal canisters were lower than 100oC, which satisfied thethermal design requirement of the disposal system. In this study, the higher peak temperature results of disposalcanisters indicated the greater thickness of bentonite buffer as the heat transfer effect get reduced. In addition, the heattransfer effect was also influenced by the distance between deposition hole and the dimension of disposal canisters. This study can be used for further research regarding Deep Geological Repository (DGR) design considering variousdisposal canisters and disposal concepts.
참고문헌 (20)
- General Standards of High Level Radioactive Waste in Deep Geological Repository, "Nuclear Safety and Security Commission Notice", ~ (2021)
- Kim J, "Global Radioactive Waste Disposal Trends and Prospects", J. Korean Soc. Environ. Eng, 45(4), pp.210~224 (2023)[DOI]
- Safety Case for the Disposal of Spent Nuclear Fuel at Olkiluoto, "Posiva Oy", 41~, pp.Posiva 2012-12 (2012)
- Canister Design 2012, "H. Raiko", 89~, pp.Posiva 2012-13 (2012)
- Conceptual Model for Developing System-level Performance Assessment, "Yoon H", 11~ (2023)
- Safety functions, performance targets and technical design requirements for a KBS-3V repository, "Joint SKB", 44~46, pp.Posiva SKB Report 01 (2017)
- ANSYS, Inc, "Thermal Analysis Guide", 4~14 (2018)
- Canister Production Line 2012, "H. Raiko", 29~, pp.Posiva 2012-16 (2012)
- DOE Advisory and Assistance Services Contract, "Task Order 18: Generic Design for Small Standardized Transportation, Aging and Disposal Canister Systems", ~ (2015)
- Multi-Pack Disposal Concepts for Spent Fuel, "Hardin E", ~, pp.FCRDNFST-2016-000640 Rev.1 (2016)
- Canister Design Concepts for Disposal of Spent Fuel and High Level Waste, "Nagra", 8~, pp.Technical Report 12-06 (2012)
- Thermo-Hydraulic Modelling of Buffer and Backfill, "Pintado X", ~, pp.Posiva 2012-48 (2012)
- Kim HC, "A Study on the Effective Utilization of Temperature Logging Data for Calculation Geothermal Gradient", Econ. Environ. Geol, 32(5), pp.503~517 (1999)
- Backfill Design 2012, "J. Autio", 25~, pp.Posiva 2012-15 (2013)
- Safety Case for the Disposal of Spent Nuclear Fuel at Olkiluoto, "Posiva Oy", 696~697, pp.Posiva 2013-01 (2013)
- Park J, "Thermal Properties of Rocks in the Republic of Korea", Econ. Environ. Geol, 42(6), pp.591~598 (2009)
- KBS-3H Design, Production and Initial State of Buffer and Filling Components, "Posiva", 71~, pp.Posiva 2016-06 (2018)
- Technical Report, "Nagra", ~ (2014)
- Buffer, Backfill and Closure Evolution, "Posiva Oy", 36~, pp.Working Report 2021-08 (2021)
- KBS-3H System Design Phase 2011-2016 : Final Report, "Posiva Oy", 21~40, pp.Posiva SKB Report 06 (2017)
