• Proceedings of the Korean Geotechical Society Conference
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• 2010.03a
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• pp.791-800
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• 2010

This paper presents the construction status and the conceptual designs of midium and high level radioactive waste disposal facilities from all around world. For the midium radioactive waste, a shallow disposal using trench or a deep depth disposal are adopted. However, these are rather focusing on the social and cultural point of view than the technical. Meanwhile, the high level radioactive waste is basically disposed in the deep underground. The corresponding ground conditions are usually dense and composed of sedimentary and crystalline rocks mainly with low permeability. A barrier system is made of canister which consists of copper, titanium, and tin. The inner and outer side of the canister are composed of different materials respectively.

• Proceedings of the Korean Society of Soil and Groundwater Environment Conference
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• 2003.09a
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• pp.587-591
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• 2003

방사성폐기물 처분연구의 일환으로 결정질 암반에서의 지하수의 함양특성을 알아보기 위하여 연구지역의 강수량, 지표유출량 및 지하수위 변동량을 시간별로 일정기간동안 모니터링하였고 채취된 강수, 지표수 및 지하수의 수소동위원소 분석을 수행하였다. 강수사건 (Rainfall event)에 따른 지표유출량과 지하수위는 급격히 증가되며, 지하수위는 약 1일경과 후 최대값을 갖는다. 연구지역 5개 시추공으로부터 모니터링된 지하수위결과는 강수사건에 따라 지하수위의 증감특성을 보여주나, 변화되는 양상은 시추공의 수리특성에 따라 다르게 나타난다. 지표수 및 지하수의 수소동위원소조성은 강수사건에 따라 상응하여 변화되고 있어, 강수, 지표수 및 지하수의 양적변화와 함께 동위원소결과의 해석은 지하수의 함양특성을 정량적으로 추정할 수 있을 것이다.

• Computational Structural Engineering
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• v.4 no.4
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• pp.117-124
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• 1991

In order to predict properly the effects of ground motion associated with earthquakes on underground radioactive waste disposal facilities, an understanding of the structural behavior of an underground opening in discontinuous rock masses subjected to dynamic loadings is essential. This paper includes literature review on computational models for discontinuous rock masses and on mathematical models for the structural analysis of underground opening. Then, structural analyses of underground openings using the distinct element computer program written for the static and dynamic analysis of discontinuous rock masses have been performed.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05a
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• pp.609-614
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• 1998

고준위 방사성 폐기물 처분과 관련이 있는 가속기구동 소멸처리로는 미임계로이기 때문에 별도의 중성자원이 필요하다. 가속기에서 나오는 양성자를 받아 중성자를 발생시키는 중성자원으로 사용될 표적물로서 거론되는 방안중에 하나인 고체표적시스템에 대한 열전달 예비계산을 수행하였다. 고체표적물의 물질은 텅스텐을 대상으로 하였으며 표적시스템은 원통형구조를 가정하였다. 양성자 조사에 의한 텅스텐 물질의 핵파쇄반응으로 인한 내부발열을 모사하여 표적물내에서의 온도상승속도와 온도분포를 조사하였다. 계산결과 별도의 표적물에 대한 냉각시스템이 없는 상황에서 30∼37초만에 국부적으로 텅스텐의 온도가 녹는점 이상으로 상승하는 결과를 보였다. 따라서 고체표적물 시스템을 소멸처리로에서 사용하기 위해서는 표적물을 냉각시키기 위한 다각도의 방안이 모색되어야 한다.

• Journal of the Korean Ceramic Society
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• v.25 no.2
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• pp.101-110
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• 1988

In order to improve the physical properties of concrete used for treatment and disposal container of low-and intermediate-level radioactive wastes, OPC (ordinary portland cement), ACPC (asphalt coated portland cement) and EPC(epoxy-portland cement) concrete specimens were prepared, and the physical properties of each concrete specimen were tested. According to the experimental results, EPC concrete showed better physical properties than ACPC and OPC concrete, however, ACPC concrete proved to be a best material for treatment and disposal container of radwastes in view of economic aspect and physical properties.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05b
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• pp.643-650
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• 1997

경제성장과 생활향상에 따라 증가일로에 있는 전력에너지를 효율적으로 공급하기 위해서는 원자력발전소의 증설이 불가피하다고 판단하여 정부는 이에 대한 중장기계획을 수립하여 추진하고 있다. 아울러 원전에서 발생하는 방사성폐기물을 처분할 시설의 입지를 위해서도 수차에 걸쳐 노력을 하여왔다. 그러나, 1970년대에 건설이 이미 완료되었거나 건설을 착수한 것 외에는 원자력시설의 입지에 지금까지 성공한 것이 없다. 입지실패의 원인 중 하나는 그간 입지정책을 추진해 오는 과정에서 입지 접근방식에 대한 검토가 부족하여 입지전략이 제대로 수립되지 않았던 때문인 것으로 사료된다. 본 연구는 원자력시설을 입지시키기 위해 널리 활용되어 온 시설입지 접근방식들을 구체적으로 고찰하여 시설입지에 대한 반발현상을 체계적으로 이해함으로써 원자력시설의 성공적인 입지에 첩경이 되고자 하는데 그 목적이 있다. 연구 결과, 성공적인 시설입지를 위해서는 어느 하나의 특정 접근방식에만 주안점을 둔 전략 모색은 결코 바람직하지 못하고 입지추진단계와 절차 및 대상 등에 따라 세 가지 접근방식을 적절하게 활용하는 전략을 모색하여야만 시설입지에 대한 반발을 효과적으로 극복하고 시설을 성공적으로 입지시킬 수 있을 것으로 판단된다.

• Journal of the Korean Geotechnical Society
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• v.19 no.5
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• pp.211-221
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• 2003

At Aspo hard rock laboratory in Sweden, an in-situ heater experiment called "$\"{A}"{s}"{p}"{o}$ Pillar Stability Experiment (APSE)" is prepared to assess capability to predict spatting and stability in a rock mass between deposition holes for radioactive waste. To Predict reasonably fracturing process at rock pillar under a planned configuration before testing, a boundary element code FRACOD has been applied for modelling. The code has been improved to simulate explicitly fracture evolution both at rock boundaries and in intact rocks. A new inverse stress reconstruction technique using boundary element has been also developed to transfer stress field by excavation and thermal loading into the FRACOD model. This article presents the results from predictive modelling far the planned in-situ test condition. Excavation induced stresses might cause slight fracturing in the pillar walls. Typical shear fractures have been initiated and propagated near central pillar walls during 120 days of heating, but overall rock mass remained stable under the considered configuration. The effects of pre-existing joints and properties of fractures are also discussed. It is found from the results that FRACOD can properly model essential rock spatting and propagation at deep tunnels and boreholes.at deep tunnels and boreholes.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.12 no.1
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• pp.69-77
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• 2014

Unsaturated hydraulic conductivity of the bentonite-buffer was evaluated using the relative humidity data. The method for calculating unsaturated hydraulic conductivity was deduced from the general analytical equation representing the movement of water in unsaturated media, which was applied to the experimental results of water infiltration tests for identifying the behavior of unsaturated hydraulic conductivity according to the water saturation. Unlike the saturated condition, the hydraulic gradient and water flux were irregularly changed, and the unsaturated hydraulic conductivity was increased with increasing the experimental time. Swelling of bentonite grains due to the water absorption increased the volume and size of pore within bentonite, resulting in the increase of water velocity and unsaturated hydraulic conductivity. This result suggested the necessity of further investigation on the correlation between the swelling degree of bentonite-buffer and unsaturated hydraulic conductivity. The method used in this study can be useful technique for evaluating long-term hydraulic performance of bentonite-buffer in the radioactive waste disposal system.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.261-267
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• 2004

Inventories, projections, and characteristics of spent nuclear fuel(SNF) generated from domestic nuclear power plants were updated to support high-level waste disposal system design. The historical and projected inventory by the end 2055 is expected to be 20,500 and 14,800MTU for PWR and CANDU spent nuclear fuel, respectively The ratio of quantity for TEX>$17{\times}17$ SNF was shown to be 0.6 as of 2003. The amount of TEX>$17{\times}17$ SNF, however, will be less than that of TEX>$16{\times}16$ KSFA after 2012, while the quantity of TEX>$16{\times}16$ KSFA will reach to 70% of the total spent fuels in the 2055. Average turnup of SNF revealed ~36GWD/MTU and ~40GWD/MTU for the period of 1994-1999 and 2000-2003, respectively. It is expected that the average burnup of SNF will exceed 45GWD/MTU at the end of 2000's. Therefore, it seems reasonable to use the TEX>$17{\times}17$ 4.5w/o, 45GWD/MTU as the Reference SNF at present state. The TEX>$16{\times}16$ KSFA 4.5w/o, 55GWD/MTU, however, should be Reference SNF after ~2010.

• Korean System Dynamics Review
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• v.9 no.2
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• pp.105-128
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• 2008

City of Gyeongju's referendum finally offered the long-waited low-level radioactive waste disposal site in November 2005. Gyeongju's positive decision was due to the various economic rewards and incentives the national government promised to the city. 300 billion won for an accepting bonus, the location of the headquarter building of the Korean Hydro and Nuclear Power Co., and the accelerator research center and 3.25 trillion won for supporting regional development program implementation. All of the above will affect the city's infrastructure and the citizens' economic and social lives. Population, land use, economic structure, SOC and quality of life will be affected. Some will be very positive, and some will be negative. This research project will see the future of the city and forecast the demographic, economic, physical and environmental changes of the city via computer simulation's system dynamics technique. This kind of simulation will help City of Gyeongju's what to prepare for the future. The population forecasting of the year 2046 will be 662,424 with the waste disposal site, and 327,274 without the waste disposal site in Gyeongju. The waste disposal site and regional supporting program will increase 184,246 Jobs more with 1,605 agriculture and fishery, 5,369 manufacturing shops and 27,577 shops. The population increase will bring 96,726 more houses constructed in the city. Land use will also be affected. More land will be developed. And road, water plant and waste water plant will be expanded as much. The city's financial structure will be expanded, due to the increased revenues from the waste disposal site, and property tax revenues from the middle-class employees of the company, and the high-powered scientists and technologists from the accelerator research center. All in all, the future of the city will be brighter after operating the nuclear waste disposal site inside the city.