Concepts of heat dissipation of a disposal canister and its computational analysis
2
조회
0
다운로드
1
인용
0
참고문헌
키워드
초록
The stability of engineered barriers in high-level radioactive waste disposal systems can be influenced by the decay heat generated by the waste. This study focuses on the thermal analysis of various canister designs to effectively lower the maximum temperature of the engineered barrier. A numerical model was developed and employed to investigate the heat dissipation potential of copper rings placed across the buffer. Various canister designs incorporating copper rings were presented, and numerical analysis was performed to identify the design with the most significant temperature reduction effect. The results confirmed that the temperature of the buffer material was effectively lowered with an increase in the number of copper rings penetrating the buffer. Parametric studies were also conducted to analyze the impact of technical gaps, copper thickness, and collar height on the temperature reduction. The numerical model revealed that the presence of gaps between the components of the engineered barrier significantly increased the buffer temperature. Furthermore, the reduction in buffer temperature varied depending on the location of the gap and collar. The methods proposed in this study for reducing the buffer temperature hold promise for contributing to cost reduction in radioactive waste disposal.
Abstract
The stability of engineered barriers in high-level radioactive waste disposal systems can be influenced by the decay heat generated by the waste. This study focuses on the thermal analysis of various canister designs to effectively lower the maximum temperature of the engineered barrier. A numerical model was developed and employed to investigate the heat dissipation potential of copper rings placed across the buffer. Various canister designs incorporating copper rings were presented, and numerical analysis was performed to identify the design with the most significant temperature reduction effect. The results confirmed that the temperature of the buffer material was effectively lowered with an increase in the number of copper rings penetrating the buffer. Parametric studies were also conducted to analyze the impact of technical gaps, copper thickness, and collar height on the temperature reduction. The numerical model revealed that the presence of gaps between the components of the engineered barrier significantly increased the buffer temperature. Furthermore, the reduction in buffer temperature varied depending on the location of the gap and collar. The methods proposed in this study for reducing the buffer temperature hold promise for contributing to cost reduction in radioactive waste disposal.
참고문헌 (31)
- Long-term Evolution of GyeongJu Bentonite Buffer in KURT Underground Environment, "M. Lee", KAERI, ~, pp.TR-8011 (2020), 2020
- V. K. Sharma, "The oxidation of Cu(I)in electrolyte solutions", J. Solut. Chem, 17(6), pp.581~599 (1988)
- M. Manaka, "The effective diffusion coefficient of dissolved oxygen and oxidation rate of pyrite by dissolved oxygen in compacted purified and crude sodium bentonites in carbonate buffered solution", Nucl. Technol, 143(3), pp.335~346 (2003)
- M. Martın, "Diffusion of soluble salts under a temperature gradient after the hydration of compacted bentonite", Appl. Clay Sci, 17(1–2), pp.55~70 (2000)
- Impact of Elevated Temperatures on Bentonite Buffers, "J. Wilson", ~, pp.QRS-1384Q-R3 Version 1.2 (2016)
- L. Zheng, "Coupled THMC models for bentonite in an argillite repository for nuclear waste : illitization and its effect on swelling stress under high temperature", Eng. Geol, 230, pp.118~129 (2017)
- Technical Analysis of Design & Manufacturing of a Disposal Canister for Deep Geologic Disposal, "M. Lee", KAERI, ~, pp.-4458 (2011), 2011
- Thermal Dimensioning of the Deep Repository. Influence of Canister Spacing, Canister Power, Rock Thermal Properties and Nearfield Design on the Maximum Canister Surface Temperature, "H. H¨okmark", SKB, ~, pp.Technical Report TR-03-09 (2003)
- 이종표, "국산 압축벤토나이트 완충재의 첨가제 혼합을 통한 열전도도 향상", Journal of Nuclear Fuel Cycle and Waste Technology, 11(1), pp.11~21 (2013), 한국방사성폐기물학회[DOI]
- Review of the Current Status of Work on Enhanced Bentonite Buffer Materials, Vol 17, "D. Leung", AMEC, ~, pp.RWMD Project RP51 TN-E2.2 (2014)
- J. Y. Lee, "Analyses of disposal efficiency based on nuclear spent fuel cooling time and disposal tunnel", pit spacing for the design of a geological repository, 2011, pp.53(4), 361~367
- 윤석, "고준위폐기물 처분시설의 압축 벤토나이트 완충재의 열전도도 추정", 한국지반공학회논문집, 33(7), pp.55~64 (2017), 한국지반공학회
- 윤석, "압축 벤토나이트 완충재의 온도에 따른 열전도도 평가", Journal of Nuclear Fuel Cycle and Waste Technology, 18(1), pp.43~49 (2020), 한국방사성폐기물학회[DOI]
- Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan, vol. 12, "T. Jnc", Japan Nuclear Cycle Development Institute, 2000~2003 (2000)
- Improvement of the Thermal Conductivity of a Compact Bentonite Buffer, "M. Lee", KAERI, ~, pp.KAERI (2013), TR-5311[DOI]
- 이종열, "국내 원자력발전소에서의 사용후핵연료 발생 특성을 고려한 심층 처분시스템 개선", Journal of Nuclear Fuel Cycle and Waste Technology, 17(4), pp.405~418 (2019), 한국방사성폐기물학회[DOI]
- I. Kim, "Thermal Dimensioning of SiC Canister Applied A-KRS", Transactions of the Korean Nuclear Society Spring Meeting (2014)
- Y. Wang, "Enhancement of thermal conductivity of bentonite buffer materials with copper wires", meshes for high-level radioactive waste disposal, 2020, pp.206(10), 1584~1592
- 김민섭, "Identification of Mechanical Parameters of Kyeongju Bentonite Based on Artificial Neural Network Technique", Journal of Nuclear Fuel Cycle and Waste Technology, 20(3), pp.269~278 (2022), 한국방사성폐기물학회[DOI]
- S. Whitaker, "Flow in porous media I : a theoretical derivation of Darcy’s law", Transport Porous Media, 1(1), pp.3~25 (1986)
- H. C. Berg, "Random Walks in Biology" (1993), Princeton University Press
- D. P. Hodgkinson, "A mathematical model for hydrothermal convection around a radioactive waste depository in hard rock", Ann. Nucl. Energy, 7(6), pp.313~334 (1980)
- M. S. Kim, "A multi-objective optimization of initial conditions in a radioactive waste repository by numerical thermo-hydromechanical modeling", Comput. Geotech, 114, pp.103106~ (2019)
- J. O. Lee, "Coupled thermal-hydro analysis of unsaturated buffer and backfill in a high-level waste repository", Ann. Nucl. Energy, 72, pp.63~75 (2014)
- An Engineered Barrier Concept of Reference Deep Geological Disposal System for Hi-Burnup Spent Fuel, "J.Y. Lee", KAERI, ~, pp.TR-7405 (2018), 2018
- HLW Disposal System Development, "H. J. Choi", KAERI, ~, pp.RR-2765 (2006), 2006
- Long-term Evolution of GyeongJu Bentonite Buffer in KURT Underground Environment, "W.J. Cho", KAERI, ~, pp.TR-8011 (2020), 2020
- J. O. Lee, "Numerical analysis of the effect of gapfilling options on the maximum peak temperature of a buffer in an HLW repository", Prog. Nucl. Energy, 111, pp.138~149 (2019)
- F. G. Gibb, "A model for heat flow in deep borehole disposals of high-level nuclear waste", J. Geophys. Res. Solid Earth, 113(B5) (2008)
- X. Li, "Simulations of THM processes in buffer-rock barriers of high-level waste disposal in an argillaceous formation", J. Rock Mech. Geotech. Eng, 5(4), pp.277~286 (2013)