• Proceedings of the Korean Radioactive Waste Society Conference
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• 2012.05a
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• pp.373-374
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• 2012

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.377-385
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• 2004

The quantity of radioactive waste generated from HANARO operation for the years of 1996 to 2003 has been analysed. It was found that the solid waste of $72, 999{\ell}$ and liquid waste of $263, 576{\ell}$ have been generated for the past 8 years. The amounts of Ar-41, I-131 and H-3 exhausted to the environment were 1, 225.6 Ci, 1.612E-2 Ci and 210 Ci, respectively.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.243-244
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• 2004

금속성 방사성폐기물을 제염하는 설비의 조건으로는 제염계수, 2차 폐기물 발생량, 모재의 회수가능성, 작업자의 안전성(원격조정) 등을 고려하여야 한다. 금속성 방사성폐기물의 오염제거 방법으로 습식제염 방법을 손쉽게 생각할 수 있으나 습식제염은 모재로부터 오염 물질을 선택적으로 제염이 불가능하고 강산 용액을 사용하므로 제염후 발생되는 2차 액체폐기물로 인해 최근 그 적용이 제한되고 있다.(중략)

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.1 no.1
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• pp.1-10
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• 2003

As a follow up to the Agenda 21's policy statement for safe management of radioactive waste adopted at Rio Conference held in 1992, the UN invited the LAEA to develop and implement indicators of sustainable development for the management of radioactive waste. The IAEA finalized the indicators in 2002, and is planning to calculate the member states' values of indicators in connection with operation of its Net-Enabled Waste Management Database system. In this paper, the basis for introducing the indicators into the radioactive waste management was analyzed, and calculation methodology and standard assessment procedure were simply depicted. In addition, a series of innate limitations in calculation and comparison of the indicators was analyzed. According to the proposed standard procedure, the indicators for a few major countries including Korea were calculated and compared, by use of each country's radioactive waste management framework and its practices. In addition, a series of measures increasing the values of the indicators was derived so as to enhance the sustainability of domestic radioactive waste management program.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05b
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• pp.813-818
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• 1995

방사성 폐기물 처분장의 확률론적 안전성 분석은 방사성 폐기물 처분장의 운영에 앞서 수행되어야 할 과제이다. 따라서, 본 연구에서는 폐기물 처분장의 확률론적 안전성 분석을 체계적으로 수행하기 위한 방법론을 개발하여 제시하였다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.252-253
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• 2004

원자력발전소를 가동한지 25년이 지나고 있는 현재 방사성 폐기물에 대한 대책이 시급한 실정이다. 가동한지 오래된 국내 원자력발전소의 경우 가까운 장래에 일차 냉각 계통의 제염이 요구될 것이며, 특히 앞으로 해체를 해야 할 시설들이 생기고 철거를 해야 할 필요성이 제기 되면서 엄청나게 발생할 금속 폐기물의 처리에 대한 문제가 주목을 받고 있다. 금속 폐기물의 처리를 위해 부피를 최소화하여 처분 관리하는 방법과 금속 폐기물을 제염하여 재사용하는 방법 등이 고려되고 있다.(중략)

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2012.05a
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• pp.25-26
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• 2012

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2012.05a
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• pp.39-40
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• 2012

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2009.06a
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• pp.184-185
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• 2009

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.15 no.3
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• pp.265-279
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• 2017

The Gyeongju underground silo type disposal facility, approved for use in December 2014, is in operation for the disposal of low and very low-level radioactive wastes, excluding intermediate-level waste. That is why the existing low-level radioactive waste level has been subdivided and the concentration limit value for intermediate-level waste has been changed in accordance with Nuclear Safety Commission Notice 2014-003. For the safe disposal of intermediate-level wastes, new optimization methodology for calculating the concentration limit of intermediate radioactive level wastes at an underground silo type disposal facility was developed. According to the developed optimization methodology, concentration limits of intermediate-level wastes were derived and the inventory of radioactive nuclides was evaluated. The operation and post closure scenarios were evaluated for the derived radioactive nuclide inventory and the results of all scenarios were confirmed to meet the regulatory limit. However, in case of $^{14}C$, it was confirmed that additional radioactivity limitation through a well scenario was needed in addition to the limit of disposal concentration. It was confirmed that the derived intermediate concentration limit of radioactive waste can be used as the intermediate-level waste concentration limit for the underground disposal facility. For the safe disposal of intermediate-level wastes, KORAD plans to acquire additional data from the radioactive waste generator and manage the cumulative radioactivity of $^{14}C$.