• Geotechnical Engineering
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• v.15 no.12
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• pp.19-33
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• 1999

• Tunnel and Underground Space
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• v.11 no.1
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• pp.1-13
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• 2001

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2011.05a
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• pp.369-370
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• 2011

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2007.11a
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• pp.194-195
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• 2007

• Nuclear Engineering and Technology
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• v.24 no.3
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• pp.329-335
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• 1992

장반감기 초우라늄 원소들(Am, Cm, Np 등)과 핵분열생성물들(135Cs, 129I)이 포함된 고준위 방사성폐기물을 심지층처분할 경우도 장반감기 핵종들의 장시간에 걸친 유출현상으로 인하여 환경오염이 문제가 될 가능성이 있다. 이러한 장반감기 핵종들의 심지층처분 대안으로 소멸처리 방식이 70년대부터 선진국들에서 활발히 연구되어져 왔다. 본 기고문은 이러한 소멸처리와 그 전단계인 군분리 기술의 현황과 향후 전망을 정리하고 특히 현존하는 소멸처리 방식의 문제점을 분석하여 향후 국내에서 수행할 소멸처리 연구에 도움이 되고자 하였다.

• Tunnel and Underground Space
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• v.21 no.6
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• pp.518-525
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• 2011

In this study, the natural ventilation pressure resulting from the large altitude difference which is a characteristic of high radioactive waste repository and the caloric value of the heat emitted by wastes was calculated and based on the results, natural ventilation quantities were calculated. A high radioactive waste repository can be considered as being operated through closed cycle thermodynamic processes similar to those of thermal engines. The heat produced by the heating of high radioactive wastes in the underground repository is added to the surrounding air, and the air goes up through the upcast vertical shaft due to the added heat while working on its surroundings. Part of the heat added by the work done by the air can be temporarily changed into mechanical energy to promote the air flow. Therefore, if a sustained and powerful heat source exists in the repository, the heat source will naturally enable continued cyclic flows of air. Based on this assumption, the quantity of natural ventilation made during the disposal of high radioactive wastes in a deep geological layer was mathematically calculated and based on the results, natural ventilation pressure of $74{\sim}183$Pa made by the stack effect was identified along with the resultant natural ventilation quantity of $92.5{\sim}147.7m^3/s$. The result of an analysis by CFD was $82{\sim}143m^3/s$ which was very similar to the results obtained by the mathematical method.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.11 no.3
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• pp.253-257
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• 2013

Geology, hydrogeology, and geochemistry are the main technical siting factors of a geological repository for spent nuclear fuels. This paper evaluated the siting criteria of overseas geological repository with related to hydrogeologic properties, such as hydraulic conductivity, partitioning coefficient, dispersion coefficient, boundary condition, and water age. Each country establishes the siting criteria based on its important geological backgrounds and information, and social environment. For example, Sweden and Finland that have decided a crystalline rock as a host rock of a geological repository show different siting criteria for hydraulic conductivity. In Sweden, it is preferable to avoid area where the hydraulic conductivity on a deposition hole scale (~30m) exceeds $10^{-8}m/s$, whereas Finland does not decide any criterion for the hydraulic conductivity because of limited data for it. In addition, partitioning coefficients should be less than 10-1 of average value in Swedish crystalline bedrock. However, the area where shows 100 times less than average partitioning coefficients of radionuclides in crystalline rock should be avoided in Sweden. In German, the partitioning coefficients for the majority of the long-term-relevant radionuclides should be greater than or equal to $0.001m^3/kg$. Therefore, it is strongly required to collect much and exact information for the hydrogeologic properties in order to set up the siting criteria.

• Tunnel and Underground Space
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• v.9 no.2
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• pp.102-113
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• 1999

Two-dimensional and three-dimensional DEM programs, UDEC and 3DEC, were used to investigate the mechanical stability of the conceptual design of deposition drift and deposition holes constructed in a crystalline rock mass. From the simulations, the influence of discontinuities, the number of deposition holes, and deposition hole interval on the stability of deposition drift and deposition holes could be determined. From the two-dimensional and three-dimensional analysis. it was concluded that three-dimensional analysis should be carried 7ut fur deriving reliable conclusions. Even though the deposition hole interval changed from 8 m to 3 m, which did not damage the mechanical stability of the deposition drift.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2008.11a
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• pp.84-85
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• 2008

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2005.11a
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• pp.207-209
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• 2005