• Nuclear industry
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• v.22 no.1 s.227
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• pp.30-36
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• 2002

• Tunnel and Underground Space
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• v.11 no.2
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• pp.79-95
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• 2001

• Nuclear industry
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• v.26 no.2 s.276
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• pp.8-13
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• 2006

• Proceedings of the Korean Nuclear Society Conference
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• 2002.10a
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• pp.328-328
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• 2002

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.300-305
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• 2003

One of the most important parts in constructing radioactive waste repository may be its safety aspect. The fundamental function of the repository is to isolate completely and forever the radioactive wastes disposed of in it. However, since either normally or abnormally nuclides are to be released from the repository with a certain causes. The hydraulic conductivity is related to transportation of nuclide in soil. However, hydraulic characteristics research in unsaturated soil is not enough at present time. A fast and easy procedure for estimating unsaturated flow parameters is presented. The estimation is based on direct measurement of the retention characteristics combined with inverse estimation of the hydraulic conductivity characteristics from one-step outflow experiment.

• Proceedings of the Korean Society for Rock Mechanics Conference
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• 2006.09a
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• pp.3-14
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• 2006

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.1
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• pp.55-62
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• 2012

As an alternative of the high-level radioactive waste disposal in the subsurface repository, a deep borehole disposal is reviewed by several nuclear advanced countries. In this study, the state of the art on the borehole disposal researches was reviewed, and the possibility of borehole disposal in Korean peninsula was discussed. In the deep borehole disposal concept radioactive waste is disposed at the section of 3 - 5km depth in a deep borehole, and it has known that it has advantages in performance and cost due to the layered structure of deep groundwater and small surface disposal facility. The results show that it is necessary to acquisite data on deep geologic conditions of Korean peninsula, and to research the engineering barrier system, numerical modeling tools and disposal techniques for deep borehole disposal.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.346-346
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• 2004

차세대관리 종합공정(ACP)은 사용후핵연료의 안전하고 효율적인 관리를 위하여 제시된 건식처리공정으로 이 공정을 이용하여 사용후핵연료를 금속으로 전환하고, 고발열성 핵종(Cs, Sr)을 효율적으로 제거하여 사용후핵연료의 부피, 발열량 및 방사선의 세기를 최대 1/4까지 감소시키고, 처분용기의 소요량과 처분장의 소요면적을 1/2 이상으로 축소함으로서 처분 안전성과 경제성을 높일 수 있는 장점으로 인해 연구개발 중에 있으며, 현재 기초연구가 완료되어 실증시험 수행을 위한 상세 계획이 확정되었다.(중략)

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2007.05a
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• pp.215-216
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• 2007

원전에서 발생하는 중 저준위방사성폐기물(이하, "방폐물"이라 함)을 처분시설로 운반하는 것은 원전과 처분시설이 임해지역에 위치하고 있으므로 육상운반보다는 선박을 이용하는 해상운반이 효율적이다. 해상운반은 무엇보다 다량운반이 가능하며 이로 인하여 운반회수가 줄고, 인구밀집지역을 지나지 않아도 되기 때문에 방폐물의 운반에 대한 위험도가 상대적으로 적어 안전성 확보에 유리하다. 방폐물의 해상운반은 운반 도중 방사성물질의 위험으로부터 인간과 환경을 보호하기 위하여 국제원자력기구(IAEA)의 안전운반규정, 국제해사기구(IMO)의 국제해상위험물규칙, 국내 원자력법 등 국내외의 엄격한 기술기준에 따라 안전성이 철저하게 보장되어야만 한다. 한국수력원자력(주)(이하, "한수원"이라 함)는 원전(월성원전 제외)에서 처분시설까지 방폐물을 안전하고 효율적으로 운반하기 위하여 전용운송선박, 운반용기, 전용운반차량 및 원전 물량장 등으로 이루어지는 해상운반시스템을 구축하여 운영할 것이다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.17 no.2
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• pp.203-212
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• 2019

Disposal nonconformity of radioactive wastes refers to radioactive wastes that need to be treated, solidified and packaged during operation or decommissioning of NPPs, and are typically exemplified by particulate radioactive wastes with dispersion characteristics. These wastes include the dried powders of concentrated wastes generated in the process of operating NPPs, slurry and sludge, various powdered wastes generated in the decommissioning process (crushed concrete, decontamination sludge, etc.), and fine radioactive soil, which is not easy to decontaminate. As these particulate wastes must be packaged so that they become non-dispersive, they are solidified with solidification agents such as cement and polymer. If they are treated using existing solidification methods, however, the volume of the final wastes will increase. This drawback may increase the disposal cost and reduce the acceptability of disposal sites. Accordingly, to solve these problems, this study investigates the pelletization of particulate radioactive wastes in order to reduce final waste volume.