• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.6 no.4
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• pp.297-306
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• 2008

This study was carried out to identify the characteristics of hydrochemistry controlling groundwater chemical condition in a repository site of Gyeongju. For this study, 12 bore holes of all monitoring bore holes in the study area were selected and total 46 groundwater samples were collected with depth. In addition, 3 surfacewater samples and 1 seawater sample were collected. For water samples, cations and anions were analyzed. The environmental isotopes(${\delta}^{18}O-{\delta}D$, Tritium, ${\delta}^{13}C,\;{\cdot}{\delta}^{34}S$) were also analyzed to trace the origin of water and solutes. The result of ${\delta}^{18}O\;and\;{\delta}D$ analysis showed that surface water and groundwater were originated from precipitation. Tritium concentrations of groundwater decreased with depth but high concentrations of tritium indicated that groundwater was recharged recently. The results of ion and correlation analysis showed that groundwater types of the study area were represented by Ca-Na-$HCO_3$ and Na-Cl-$SO_4$, which was caused by sea spray and water-rock interaction. Especially, high ratio of Na content in groundwater resulted from ion exchange. For redox condition of groundwater, the values of DO and Eh decreased with depth, which indicated that reducing condition was formed in deeper groundwater. In addtion, high concentration of Fe and Mn showed that redox condition of groundwater was controlled by the reduction of Fe and Mn oxides.

• The Journal of Engineering Geology
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• v.33 no.4
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• pp.519-530
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• 2023

Moye's analytical solution was examined as a method for constant-head tests under steady-state conditions, and results were compared with transient-state analyses in in situ hydraulic tests. The sensitivity of hydraulic conductivities calculated using Moye's method increased with the length of the test section, which should be as large as possible under test conditions. Particularly in low-permeability media with less than 10^-8 m/sec of hydraulic conductivity, hydraulic conductivity is lower than that under transient-state conditions and can be recalculated by adjusting the boundary between radial and spherical flow assumed in Moye's equation. Constant-head tests performed in the research borehole at the KAERI Underground Research Tunnel (KURT) indicated that transmissivities derived from the constant-head withdrawal test under transient-state conditions in low-permeability media were higher than those derived from steady-state tests, likely because the groundwater flow boundary was smaller than the "half of the test-section length"assumed by Moye's equation. When interpreting constant-head test results for crystalline rock, the hydrogeological properties of the medium may be better understood by considering assumed conditions accompanying analysis of the steady-state condition and comparing them with results for the transient-state analysis, rather than simply assuming properties based on steady-state analyses.

• Tunnel and Underground Space
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• v.32 no.1
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• pp.30-58
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• 2022

The deep geological repository for high-level radioactive waste disposal is a multi barrier system comprised of engineered barriers and a natural barrier. The long-term integrity of the deep geological repository is affected by the coupled interactions between the individual barrier components. Erosion and piping phenomena in the compacted bentonite buffer due to buffer-rock interactions results in the removal of bentonite particles via groundwater flow and can negatively impact the integrity and performance of the buffer. Rapid groundwater inflow at the early stages of disposal can lead to piping in the bentonite buffer due to the buildup of pore water pressure. The physiochemical processes between the bentonite buffer and groundwater lead to bentonite swelling and gelation, resulting in bentonite erosion from the buffer surface. Hence, the evaluation of erosion and piping occurrence and its effects on the integrity of the bentonite buffer is crucial in determining the long-term integrity of the deep geological repository. Previous studies on bentonite erosion and piping failed to consider the complex coupled thermo-hydro-mechanical-chemical behavior of bentonite-groundwater interactions and lacked a comprehensive model that can consider the complex phenomena observed from the experimental tests. In this technical note, previous studies on the mechanisms, lab-scale experiments and numerical modeling of bentonite buffer erosion and piping are introduced, and the future expected challenges in the investigation of bentonite buffer erosion and piping are summarized.

• Proceedings of the Computational Structural Engineering Institute Conference
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• 2000.04b
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• pp.77-84
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• 2000

In this paper, the stress analysis of the cast iron insert of spent nuclear fuel disposal canister in a deep repository at 500m underground is done for the underground pressure variation. Since the nuclear fuel disposal usually emits much heat and radiation, its careful treatment is required. And so a long term safe repository at a deep bedrock is used. Under this situation, the canister experiences some mechanical external loads such as hydrostatic pressue of underground water, swelling pressure of bentonite, sudden rock movement etc.. Hence, the canister should be designed to withstand these loads. The cast iron insert of the canister mainly supports these loads. Therefore, the stress analysis of the cast iron insert is done to determine the design variables such as the diameter versus length of canister and the number and array type of inner baskets in this paper, The linear static structural analysis is done using the finite element analysis method. And the finite element analysis code, NISA, is used for the computation.

• Proceedings of the Korea Society for Energy Engineering kosee Conference
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• 2000.11a
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• pp.173-181
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• 2000

IAEA자료에 의하면 원자력 발전용 원자로는 1998년말 현재 세계 32개국에서 434기가 운전중이며, 총 출력은 3억 4889만kW인 것으로 나타났고, 이는 세계 총 발전량의 17%를 담당하는 것으로 확인되었다. 그러나 농축 우라늄 고체 핵연료를 사용하는 발전로 개념은 근본적으로 핵물질 SEU(Slightly Enriched Uranium)를 생산하기 위한 235U 농축과 노내에서 238U의 중성자 포획으로 전환.생성되는 Pu의 누적에 따른 핵확산 우려, 고준위 방사성 폐기물로 취급되는 사용후 핵연료 처리.처분에 관한 정책적.기술적 장기 전망의 불확실성, 그리고 설계기준사고인 LOCA로부터 중대사고로 이어지는 안전성 문제 등이 대두되고 있다. Th$^{233}$ /U용융염 핵연료주기를 이용하는 발전로 개념은 원자력 발전이 안고있는 고유문제들을 배제 또는 완화할 수 있는 방안으로 고려되고 있다.(중략)

• 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 Precision Engineering Conference
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• 1997.10a
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• pp.617-620
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• 1997

In this paper, the thermal stress analysis of spent nuclear fuel disposal canister in a deep repository at 500m underground is done for the underground pressure variation. Since the nuclear fuel disposal usually emits much heat and radiation, its careful treatment is required. And so a long term safe repository at a deep bedrock is used. Under this situation, the canister experiences some mechanical external loads such as hydrostatic pressure of underground water, swelling pressure of bentonite buffer, and the thermal load due to the heat generation of spent nuclear fuel in the basket etc.. Hence, the canister should be designed to designed to withstand these loads. In this paper, the thermal stress analysis is done using the finite element analysis code, NISA.

• Proceedings of the Korean Society of Soil and Groundwater Environment Conference
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• 2003.09a
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• pp.601-604
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• 2003

방사성폐기물 처분 연구의 일환으로 화강암지역내 500m 심도의 심부시추공이 착정되었으며, 다중패커시스템이 설치되어 장기적으로 심도별 지하수의 수리 및 화학특성이 모니터링 되고 있다. 지하수 수두값의 심도별 특성은 천부에서 심도 250m까지는 대체로 감소하는 경향을 보이며 250m이하에서 500m 심도까지는 증가하는 경향을 보여준다. 각 심도구간에서의 지하수 수두값은 장기적으로 일정한 값을 보여주지만, 장마기간동안 집중적으로 모니터링된 결과에 따르면 심도 370m 상부에서는 지하수 함양변화에 따라 지하수 수두가 변화되는 반면, 심부구간에서는 지하수 함양변화에 대하여 영향을 받지 않음을 보여준다.

• 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.

• Proceedings of the Korean Society of Soil and Groundwater Environment Conference
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• 2005.04a
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• pp.288-291
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• 2005

방사성폐기물 처분연구의 일환으로 단열 암반지역의 지하수 유동에 있어서 각 단열조의 투수량계수를 알아보기 위하여 연구지역에 설치된 3기의 시추공에서 초음파 검층, 정압주입시험 및 유동차원 해석을 수행하였다. 단열은 방향성, 틈의 크기 등의 그 분포 특성으로 인해 각 시험구간내의 지하수 유동에 있어서, 유동형태 및 단열투수량계수를 좌우하므로 일반적으로 수리특성에 널리 이용되는 다공성매질의 연속체 개념을 통한 해석의 적용에 신중성을 고려할 필요가 있다.