High-efficiency deep geological repository system for spent nuclear fuel in Korea with optimized decay heat in a disposal canister and increased thermal limit of bentonite

이종열; 김광일; 김인영; 주희재; 정종태; 이창수; 김정우; 조동건

doi:10.1016/j.net.2023.02.031

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자료유형: 학술저널

저자정보: 이종열 (한국원자력연구원) 김광일 (한국원자력연구원) 김인영 (한국원자력연구원) 주희재 (한국원자력연구원) 정종태 (한국원자력연구원) 이창수 (한국원자력연구원) 김정우 (한국원자력연구원) 조동건 (한국원자력연구원)

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제55권 제4호

발행연도: 2023.4

수록면: 1,540 - 1,554 (15page)

DOI: 10.1016/j.net.2023.02.031

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To use nuclear energy sustainably, spent nuclear fuel, classified as high-level radioactive waste and inevitably discharged after electricity generation by nuclear power plants, must be managed safely and isolated from the human environment. In Korea, the land area is limited and the amount of high-level radioactive waste, including spent nuclear fuels to be disposed, is relatively large. Thus, it is particularly necessary to maximize disposal efficiency. In this study, a high-efficiency deep geological repository concept was developed to enhance disposal efficiency. To this end, design strategies and requirements for a high-efficiency deep geological repository system were established, and engineered barrier modules with a disposal canister for pressurized water reactor (PWR)-type and pressurized heavy water reactor type Canada deuterium uranium (CANDU) plants were developed. Thermal and structural stability assessments were conducted for the repository system; it was confirmed that the system was suitable for the established strategies and requirements. In addition, the results of the nuclear safety assessment showed that the radiological safety of the new system met the Korean safety standards for disposal of high-level radioactive waste in terms of radiological dose. To evaluate disposal efficiency in terms of the disposal area, the layout of the developed disposal areas was assessed in terms of thermal limits. The estimated disposal areas were 2.51 km2 and 1.82 km2 (existing repository system: 4.57 km2) and the excavated host rock volumes were 2.7 Mm3 and 2.0 Mm3 (existing repository system: 4.5 Mm3) for thermal limits of 100 °C and 130 °C, respectively. These results indicated that the area and the excavated volume of the new repository system were reduced by 40–60% compared to the existing repository system. In addition, methods to further improve the efficiency were derived for the disposal area for deep geological disposal of spent nuclear fuel. The results of this study are expected to be useful in establishing a national high-level radioactive waste management policy, and for the design of a commercial deep geological repository system for spent nuclear fuels.

#Spent nuclear fuel #Deep geological disposal #Design requirements #High efficiency #Optimized decay heat #Thermal limits #Thermal hydraulic analyses #Disposal area

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