• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.17 no.2
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• pp.227-234
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• 2019

A user-friendly modeling interface is developed for a process-based total system performance assessment framework (APro) specialized for a generic geological disposal system for high-level radioactive waste. The APro modeling interface is constructed using MATLAB, and the operator splitting scheme is used to combine COMSOL for simulation of multiphysics and PHREEQC for the calculation of geochemical reactions. As APro limits the modeling domain to the generic disposal system, the degree of freedom of the model is low. In contrast, the user-friendliness of the model is improved. Thermal, hydraulic, mechanical and chemical processes considered in the disposal system are modularized, and users can select one of multiple modules: "Default process" and multi "Alternative process". APro mainly consists of an input data part and calculation execution part. The input data are prepared in a single EXCEL file with a given format, and the calculation part is coded using MATLAB. The final results of the calculation are created as an independent COMSOL file for further analysis.

• Journal of the Korean Geotechnical Society
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• v.33 no.7
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• pp.55-64
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• 2017

A geological repository has been considered one of the most adequate options for the disposal of high-level radioactive waste. A geological repository will be constructed in a host rock at a depth of 500~1,000 meters below the ground surface. The geological repository system consists of a disposal canister with packed spent fuel, buffer material, backfill material, and intact rock. The buffer is very important to assure the disposal safety of high-level radioactive waste. It can restrain the release of radionuclide and protect the canister from the inflow of groundwater. High temperature in a disposal canister is released into the surrounding buffer material, and thus the thermal transfer behavior of the buffer material is very important to analyze the entire disposal safety. Therefore, this paper presents a thermal conductivity prediction model for the Kyungju compacted bentonite buffer material which is the only bentonite produced in Korea. Thermal conductivity of Kyungju bentonite was measured using a hot wire method according to various water contents and dry densities. With 39 data obtained by the hot wire method, a regression model to predict the thermal conductivity of Kyungju bentonite was suggested.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.6 no.1
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• pp.65-72
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• 2008

The purpose of the HLW deep geological disposal is to isolate and to delay the radioactive material release to human beings and the environment for a long time so that the toxicity does not affect to the environment. The main requirements for the HLW repository design is to keep the buffer temperature below $100\;^{\circ}C$ in order to maintain its integrity. So the cooling time of spent fuels discharged from the nuclear power plant is the key consideration factors for efficiency and economic feasibility of the repository. The disposal tunnel/disposal hole spacing, the disposal area and thermal capacity required for the deep geological repository layout which satisfies the temperature requirement of the disposal system is analyzed to set the optimized spent fuels cooling time. To do this, based on the reference disposal concept, thermal stability analyses of the disposal system have been performed and the derived results have been compared by setting the spent fuels cooling time and the disposal tunnel/disposal hole spacing in various ways. From these results, desirable spent fuels cooling time in view of disposal area is derived. The results shows that the time reaching the maximum temperature within the design limit of the temperature in the disposal site is likely shortened as the cooling time of spent fuels becomes short. Also it seems that the temperature-rising and-dropping patterns in the disposal site are of smoothly varying form as the cooling time of spent fuels becomes long. In addition, it is revealed that a desirable cooling time of spent fuels is approximately 40-50 years when spent fuels are supposedly disposed in the deep geological disposal site with its structural scale under consideration in this study.

• Proceedings of the Korean Society for Rock Mechanics Conference
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• 2001.03a
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• pp.40-60
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• 2001

핵변환 후 영구 처분될 가압경수로 및 중수로용 사용후핵연료에 대한 인간 생태계에 대한 영향을, 직접 처분하는 경우와 비교해 보았다 심지층 처분된 용기에 저장된 사용 후 핵연료로부터 유출된 방사성 핵종들이 공학적 방벽을 거쳐 결정질 기반암 내 균열대를 통해 지하수의 흐름을 따라 이동하면서 , 다양한 지질 및 암종을 거쳐 생태 환경으로 도달한다는 핵종 유출 시나리오 중 가장 보수적인 시나리오인 우물 시나리오에 대한 위해도를 평가하여 상대적인 환경친화성을 정량적으로 제시하였다. 현재 국내에 가속기와 미임계형 원자로를 함께 사용하는 핵변환시스템과 임계형 원자로와 같은 핵변환 시스템이 개념적인 수준에서 개발되고 있어, 이 연구를 통해 향후 핵변환시스템 연구에서 요구되는 항목들도 기술적 개선, 경제성 제고, 환경 친화성, 그리고 수용성측면에서 제시하였다.

• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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• 2014.10a
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• pp.363-364
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• 2014

국내 에너지의 장기적인 수요상황을 볼 때 원자력 발전의 비중이 확대되는 것은 불가피 하므로 환경 친화적인 사용 후 핵연료의 관리 및 고준위 폐기물의 처분방안의 마련은 원자력의 개발만큼이나 중요하다. 이에 본 연구에서는 방사성 폐기물의 효율적인 관리와 저장 및 열제거를 위하여 최적 환기시스템을 적용한 처분장 설계를 목적으로 여러 환기시스템 설계안을 비교 분석하였다. 분석결과, 8가지 중 case 4(병렬회로)와 case 6(혼합 Diagonal 회로)의 환기효율이 우수한 결과를 나타냈으며, 이와 같은 연구를 통해 환경 친화적인 처분장의 건설이 가능할 것이다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.261-265
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• 2003

This paper proposes acceptance requirements and the corresponding implementation strategy for the near-surface repository of low- and intermediate-level radioactive wastes. The proposed requirements include details on waste classification and radionuclide concentration limitation and inventory analysis. The strategy considers a relevant linking between predisposal waste management, disposal safety assessment and the overall disposal system.

• Proceedings of the Korean Society for Rock Mechanics Conference
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• 2006.09a
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• pp.238-246
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• 2006

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2009.11a
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• pp.213-214
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• 2009

• Nuclear industry
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• no.5_6 s.7
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• pp.45-47
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• 1982

원자력평화이용의 마지막 큰 과제라 할 수 있는 고레벨방사성폐기물의 처리${\cdot}$처분에 관해 고레벨폐기물 glass 고화체의 화학적내구성(침출율, 고온수화반응 등), 조사효과, 장기저장시설의 냉각특성, 지층처분에서의 포장성(암석특성이나 투수성) 등 많은 연구가 행해지고 있는데, 여기서는 장기저장시설과 처분시설의 시스템개념에 관한 것을 알아 보기로 한다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2011.10a
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• pp.389-390
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• 2011