• 터널과지하공간
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• 제11권2호
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• pp.132-145
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• 2001

핵변환 후 영구 처분될 가압경수로 및 중수로용 사용후 핵연료에 대한 인간 생태계에 대한 영향을, 직접 처분하는 경우와 비교해 보았다. 심지층 처분된 용기에 저장된 사용후 핵연료로부터 유출된 방사성 핵종들이 공학적 방벽을거쳐 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 상대인 환경친화성을 정량적으로 제시하였다. 현재 국내에 가속기와 미임계형 원자로를 함께 사용하는 핵변환 시스템과 임계형 원자로와 같은 핵변환시스템이 개념적인 수준에서 개발되고 있어, 이 연구를 통해 향후 핵변환시스템 연구에서 요구되는 항목들도 기술적 개선, 경제성 제고, 환경 친화성, 그리고 수용성 측면에서 제시해 보았다.

• 방사성폐기물학회지
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• 제6권4호
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• pp.357-368
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• 2008

국내 최초의 중 저준위 방사성폐기물 처분시설에 대한 건설 운영허가가 지난 2008년 7월 31일 발급되었다. 이 논문에서는 중 저준위 방사성폐기물 처분시설에 대한 국내 기본 규제체계, 규제요건 및 기술기준을 제시하고, 동 시설의 안전성 확인을 위해 실제 적용된 안전심사수행절차를 주요 단계별로 기술하였다. 원자력법은 부지선정, 설계, 건설, 운영, 폐쇄 및 제도적관리 등 중 저준위 방사성폐기물 처분시설의 전과정에 대한 단계별 안전규제체계를 규정하고 있으며, 하위 법령과 교육과학기술부고시 등은 관련 세부 규제요건 및 기술기준을 규정하고 있다. 한국원자력안전기술원은 원자력관계법령에 근거한 교육과학기술부의 위탁에 따라 처분시설에 대한 안전심사를 수행하였으며, 부지 및 구조안전성, 방사선환경 영향, 운영 안전성, 계통 및 설비의 안전성, 품질보증, 종합안전성평가 등 세부 기술 분야별 적합성을 종합적으로 검토하였다. 전체 안전심사 과정은 사전준비단계, 초기심사단계, 본심사단계, 완료단계 등으로 구분할 수 있으며, 한국원자력안전기술원의 심사결과는 원자력안전전문위원회 5개 전문분과의 심의를 거쳐 교육과학기술부에 보고되었고, 교육과학기술부는 원자력안전위원회의 최종 심의를 통해 처분시설에 대한 건설 운영허가를 발급하였다. 이후 처분시설의 안전성은 원자력관계법령에 규정된 일련의 규제검사 및 심사를 통해 확인될 것이며, 건설 운영자의 지속적인 안전성증진계획 이행을 통해 장기적인 안전성 증진과 안전사례에 대한 신뢰구축이 가능할 것이다.

• 한국시스템다이내믹스학회:학술대회논문집
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• 한국시스템다이내믹스학회 2006년도 춘계학술대회 발표논문집
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• pp.123-149
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• 2006

본 연구는 방사성폐기물 처분시설(radioactive waste repository)의 입지를 가정하여, 처분시설이 경상북도 경주시에 발생시키는 경제적, 사회적 효과를 분석하는데 목적이 있다. 정부는 처분장 유치의 유인책(incentives)으로서 경주 지역주민들을 위하여 다양한 정책적 수단을 마련하였다. 처분시설 입지에 따른 특별지원금 3,000 억원 지원, 수거물 반입 수수료 지원(년당 50-100억원), 한국수력원자력(주) 본사이전, 양성자가속기 사업 추진 등이 그것이다. 이들 지원사업들이 가져오는 변화를 시스템 다이내믹스(System Dynamics) 기법을 적용하여 지역사회의 인구, 산업, 토지, SOC, 지방재정 등이 어떻게 변화하는지 추적해 봄으로써 도시체제의 동태성(urban system dynamics)을 이해하고 처분장 시설이 지역에 입지했을때, 미래에 발생 가능한 문제점이 없는지 밝혀내고자한다. 이를 위하여 시뮬레이션 모델링에 입지 지역의 특성과 현황을 반영하여 처분장입지에 따른 지역의 동태적인 변화과정과 경향을 추정해 보고, 현재 예정되어 있는 지원사업이 충분한지, 이외에 다른 정책적 지원이 필요한지를 알아본다. 본 연구의 의미는 이처럼 경주지역 주민들이 처분장의 지역입지를 만족스럽게 행각하고 소외감 없이 생활을 영위할 수 있도록 정책적 지원 프로그램을 작성하는데 기초가 되는 연구라는 점에 있다고 하겠다.

• 한국지반공학회:학술대회논문집
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• 한국지반공학회 2009년도 춘계 학술발표회
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• pp.792-797
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• 2009

The stress-strain characteristics of compacted bentonite are investigated using experimental triaxial compression test by Hoek-cell. Special attention given to various dry density and water absorption ratio. Based on the test results, it is shown that the stress-strain relationship of compacted bentonite is highly influenced by dry density and water absorption ratio. Also, characteristics of Bentonite is similar to the clay rather than sand. Strength of compressed Bentonite increases with higher dry density. It shows maximum strength value, if in a same condition with dry density and constrain pressure. So we determine that value as the optimistic moisture contents for the maximun strength of compressed Bentonite.

• Nuclear Engineering and Technology
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• 제29권3호
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• pp.260-268
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• 1997

The effects of three mechanisms, calcium depletion, sulphate and carbonate penetration, on the concrete degradation have been studied. The shrinking core model (SCM) and the HYDROGEOC. HEM (HGC) model have been applied to evaluate how fast the mechanisms proceed. The SCM is an analytical approximation model and the HGC is a numerical mass transport model coupled with chemical reaction. The SCM leads to more conservative results than the HGC, and turns out to be very useful in the viewpoint of simplicity and conservatism. During 300 years, calcium has been depleted within 10 cm from the concrete outer surface, and sulphate has penetrated less than 13.5 cm into the concrete. Carbonate has not penetrated own 7 cm into the concrete in contact with the bentonite, and, furthermore, its penetration into the concrete with the groundwater is negligible. Conclusively, the concrete is expected to maintain its integrity for at least 300 years that are regarded as institutional control period of intermediate and low-level radioactive waste repository.

• Journal of Radiation Protection and Research
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• 제15권2호
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• pp.101-112
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• 1990

For the performance assessment of the radioactive waste disposal system (repository), a biosphere model is suggested. This biosphere model is intended to calculate the annual doses to man caused by the contaminated river water for eight pathways and four radionuclides. This model can also be applied to assess the radiological effects of contaminated well water. To account for the uncertainties on the model parameter values, parameter distributions are assigned to these model parameters. Then, Monte Carlo simulation method with Latin Hypercube sampling technique is used. Also, sensitivity analysis is performed by using the Spearman rank correlation coefficients. It is found that these methods are a very useful tool to treat uncertainties and sensitivities on the model parameter values and to analyze the biosphere model. A conversion factor is proposed to calculate the annual dose rate to humans arising from a unit radionuclide concentration in river water. This conversion factor allows for the substitution of the biosphere model in a probabilistic performance assessment computer code by one single variable.

• 방사성폐기물학회지
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• 제18권spc호
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• pp.37-50
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• 2020

In this paper, an overview of the scoping calculation results is provided with respect to criticality and radiation shielding of two KBS-3V type PWR SNF disposal systems and one NWMO-type CANDU SNF disposal system of the improved KAERI reference disposal system for SNFs (KRS⁺). The results confirmed that the calculated effective multiplication factors (k_eff) of each disposal system comply with the design criteria (< 0.95). Based on a sensitivity study, the bounding conditions for criticality assumed a flooded container, actinide-only fuel composition, and a decay time of tens of thousands of years. The necessity of mixed loading for some PWR SNFs with high enrichment and low discharge burnup was identified from the evaluated preliminary possible loading area. Furthermore, the absorbed dose rate in the bentonite region was confirmed to be considerably lower than the design criterion (< 1 Gy·hr^-1). Entire PWR SNFs with various enrichment and discharge burnup can be deposited in the KRS⁺ system without any shielding issues. The container thickness applied to the current KRS⁺ design was clarified as sufficient considering the minimum thickness of the container to satisfy the shielding criterion. In conclusion, the current KRS⁺ design is suitable in terms of nuclear criticality and radiation shielding.

• Geomechanics and Engineering
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• 제2권3호
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• pp.213-227
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• 2010

Compacted layers of sand-bentonite mixtures have been proposed and used in a variety of geotechnical projects as engineered barriers for the enhancement of impervious landfill liners, cores of zoned earth dams and radioactive waste repository systems. This paper presents a study on the valorization of local materiel such as dune sand from Laghouat region and mine bentonite intended for the realization of liner base layers in the conception of insulation barriers for hazardous waste centers. In the practice we try to get an economical mixture that satisfies the hydraulic and mechanical properties specified by regulation rules. The effect of the bentonite additions on the mixture is reflected by its capability of clogging the matrix pores upon swelling. In order to get an adequate dune sand-bentonite mixture, an investigation on hydraulic and mechanical behaviours is carried out in this study for different mixtures. Using oedometer test, the adequate bentonite addition to the mixture, which satisfies the conditions on permeability, is found to be around 12% to 15%. These results are also confirmed by direct measurement using triaxial cell.

• 방사성폐기물학회지
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• 제19권4호
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• pp.517-532
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• 2021

Safe geological disposal of spent nuclear fuel (SNF) requires knowledge of the deep hydrochemical characteristics of the repository site. Here, we conducted a set of deep hydrochemical investigations using a 750-m borehole drilled in a model granite system in Wonju, South Korea. A closed investigation system consisting of a double-packer, Waterra pump, flow cell, and water-quality measurement unit was used for in situ water quality measurements and subsequent groundwater sampling. We managed the drilling water labeled with a fluorescein dye using a recycling system that reuses the water discharged from the borehole. We selected the test depths based on the dye concentrations, outflow water quality parameters, borehole logging, and visual inspection of the rock cores. The groundwater pumped up to the surface flowed into the flow cell, where the in situ water quality parameters were measured, and it was then collected for further laboratory measurements. Atmospheric contact was minimized during the entire process. Before hydrochemical measurements and sample collection, pumping was performed to purge the remnant drilling water. This study on a model borehole can serve as a reference for the future development of deep hydrochemical investigation procedures and techniques for siting processes of SNF repositories.

• 방사성폐기물학회지
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• 제20권2호
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• pp.231-241
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• 2022

Several countries, including Korea, are considering the direct disposal of spent nuclear fuels. The radiological safety assessment results published after a geological repository closure indicate that the instant release is the main radiation source rather than the congruent release. Three Safety Case reports recently published were reviewed and the IRF values of seven long-lived radionuclides, including relevant experimental results, were compared. According to the literature review, the IRF values of both the CANDU and low burnup PWR spent fuel have been experimentally measured and used reasonably. In particular, the IRF values of volatile long-lived nuclides, such as ¹²⁹I and ¹³⁵Cs, were estimated from the FGR value. Because experimental leaching data regarding high burnup spent nuclear fuels are extremely scarce, a mathematical modelling approach proposed by Johnson and McGinnes was successfully applied to the domestic high burnup PWR spent nuclear fuel to derive the IRF values of iodine and cesium. The best estimate of the IRF was 5.5% at a discharge burnup of 55 GWd tHM^-1.