The WRK (Waste Repository Korea bentonite) compacted bentonite medium has been considered as the appropriate buffer material in the Korean SNF (Spent nuclear fuel) repository site. In this study, hydraulic properties of the WRK compacted bentonite core (4.5 cm in diameter and 1.0 cm in length) as the buffer material were investigated in laboratory experiments. The porosity and the entry pressure of the water saturated core at different confining pressure conditions were measured. The average velocity of water flow in the WRK compacted bentonite core was calculated from results of the breakthrough curves of the CsI aqueous solution and the hydraulic conductivity of the core was also calculated from the continuous flow core experiments. Because various gases could be generated by continuous SNF fission, container corrosion and biochemical reactions in the repository site, the gas migration property in the WRK compacted bentonite core was also investigated in experiments. The gas permeability and the average of gas (H2) in the core at different water saturation conditions were measured. Laboratory experiments with the WRK Compacted bentonite core were performed under conditions simulating the DGR environment (confining pressure: 1.5- 20.0 MPa, injection pressure: 1.0-5.0 MPa, water saturation: 0-100%). The WRK Compacted bentonite core was saturated at various confining pressure conditions and the porosity ranged from 27.5% to 43.75% (average: 36.75%). The calculated hydraulic conductivity (K) of the core using experimental results was 8.69×10-11 cm/s. The gas permeability of the core when the water saturation 0~58 % was ranged of 19.81~3.43×10-16 m2, representing that the gas migration in the buffer depends directly on the water saturation degree of the buffer medium. The average gas velocity in the core at 58% of water saturation was 9.8×10-6 m/s, suggesting that the gas could migrate fast through the buffer medium in the SNF repository site. Identification of the hydraulic property for the buffer medium, acquired through these experimental measurements is very rare and is considered to have high academic values. Experimental results from this study were used as input parameter values for the numerical modeling to simulate the long-term gas migration in the buffer zone and to evaluate the feasibility of the buffer material, controlling the radionuclide-gas migration in the SNF repository site.

With the increase of temporarily-stored radioactive waste in Korea, the disposal of radioactive waste in a deep geological repository, which is located in crystalline rock at a depth of hundreds of meters below the ground level, has received great attention nowadays. To ensure the permanent isolation of radionuclides from the human and surrounding ecosystems, the safety assessment for the high-level radioactive waste disposal facilities is essential. For the reliable safety assessment of fractured rock, it is especially important to input proper hydraulic properties of fractures such as aperture and hydraulic conductivity, which can directly affect the fluid flow and radionuclide transport. Meanwhile, it has become important to consider sudden fault behavior caused by an earthquake with the recent occurrence of high-intensity earthquakes in the Korean Peninsula. The sudden fault behavior can induce the changes of the hydraulic properties of fractures. Since the changes of the hydraulic properties directly affects to the radionuclide transport in the fractured rock, it is important to estimate the effect of earthquake-induced stress change on hydraulic properties of fractures in the perspective of long-term safety assessment. In this study, the effect of an earthquake on the hydraulic properties of fractures was explored by a numerical approach. The static Coulomb stress change after the earthquake was calculated using software ‘Coulomb 3’ developed by United States Geological Survey (USGS) with the assumption for several mechanical properties such as Young’s modulus, Poisson’s ratio and effective coefficient of friction. The final stress after earthquake occurrence was calculated as the sum of the initial stress and the stress change. Thereafter, the normalized transmissivity of fracture after the earthquake was calculated using the final stress from the stress-transmissivity relationship. Using the methodology for calculating fracture transmissivity change induced by the earthquake developed in this study, the effect of several factors, such as the earthquake magnitude and the distance between fracture and epicenter, was additionally explored. The newly developed methodology will be applied to the processbased total system performance assessment framework (APro) being developed by KAERI, and this study is expected to be helpful for the safety assessment considering long-term evolution phenomena including earthquakes.

한국원자력연구원 부지 내에 위치한 지하처분연구시설(KAERI Underground Research Tunnel, KURT) 에서는 선진핵주기 고준위폐기물처분시스템(A-KRS)을 기반으로 고준위방사성폐기물을 처분하였을때, 예상되는 공학적방벽(Engineered Barrier System, EBS)과 자연방벽(Natural Barrier System, NBS)에서의 열-수리-역학적 복합거동(Thermo-Hydro-Mechanical coupled behavior)의 특성을 규명하고자 현장시험(In-situ Demonstration of Engineered Barrier System, In-DEBS)을 2012년부터 계획 및 설계를 시작하여, 2016년 5월부터 지하처분연구시설 3번 연구 갤러리(Research gallery 3)에서 진행하고 있다. 현장시험의 데이터를 분석하고 열-수리-역학적 복합거동 특성을 명확히 규명하기 위해서는 경주 벤토나이트와 KURT 암석 및 암반의 열적, 수리적, 그리고 역학적 물성 특성을 반드시 파악하고 있어야만 한다. 이에 본 연구에서는 지금까지 수행된 KURT 부지 특성과 KURT 화강암 및 경주 벤토나이트의 열적, 수리적, 그리고 역학적 특성을 정리하고, 열적, 수리적, 그리고 역학적 모델을 제시하였다. 특히, 온도에 따른 암석의 열팽창계수 변화, 응력에 따른 암석의 투수계수 변화, 포화도에 따른 벤토나이트 및 암석의 열전도도 변화, 포화도에 따른 벤토나이트의 비열 및 흡입력 변화와 같은 열-수리-역학적 복합물성에 대한 다양한 모델을 도출함으로써, In-DEBS 현장시험 결과 분석과 열-수리-역학적 복합거동 특성 평가를 위해 수행 될 수치시험에 필요한 벤토나이트와 암석 및 암반의 입력자료를 제시하고자 하였다.

This paper describes the results of the application of Cr-Diamond-like carbon (DLC) films for efficiency improvement through surface modification of spur gear parts in the hydraulic gear pump. Cr-DLC films were successfully deposited on SCM 415 substrates by a hybrid coating process using linear ion source (LIS) and magnetron sputtering method. The characteristics of the films were systematically investigated using FE-SEM, nano-indentation, sliding tester and AFM instrument. The microstructure of Cr-DLC films turned into the dense and fine grains with relatively preferred orientation. The thickness formed in our Cr buffer layer and DLC coating layer were obtained the 487 nm and . The average friction coefficient of Cr-DLC films considerably decreased to 0.15 for 0.50 of uncoated SCM415 material. The hardness and surface roughness of Cr-DLC films were measured 20 GPa and 10.76 nm, respectively. And then, efficiency tests were performed on the hydraulic gear pump to investigate the efficiency performance of the Cr-DLC coated spur gear. The experimental results show that the volumetric and mechanical efficiency of hydraulic gear pump using the Cr-DLC spur gear were improved up to 2~5% and better efficiency improvement could be attributed to its excellent microstructure, higher hardness, and lower friction coefficient. This conclusion proves the feasibility in the efficiency improvement of hydraulic gear pump for industrial applications.

고준위방사성폐기물 처분장의 완충재 후보물질 선정을 위해 경주 벤토나이트를 대상으로 수리특성, 팽윤특성, 열적특성, 역학특성 및 핵종유출 저지특성을 조사하였다. 실험결과, 압축 벤토나이트의 수리전도도는 m/s 이하로 매우 낮았으며 건조밀도가 증가할수록 감소하였다. 팽윤압은 0.66 ㎫∼14.4 ㎫ 사이의 값을 보였으며 건조밀도에 따라 증가하였다. 건조밀도가 1.4 Ms/㎥ ∼ 1.8 Mg/㎥1.4 일때, 열전도도, 열축압축강도 (unconfined compressive strength), 탄성계수 (Young's modulus of elasticity), Poisson 비는 각각 0.80 ㎉/m ∼1.52 ㎉/m , 0.55 ㎫ ∼ 8.83 ㎫, 59 ㎫ ∼ 1275 ㎫, 0.05 ∼ 0.20의 값을 나타내었다. 압축벤토나이트에 대한 핵증 확산계수는 산화 환경에서 측정되었으며, 주어진 실험조건에서 삼중수소 (H-3)는 1.7 /s ∼ 3.4 /s. 양이온 핵종 (Cs, Sr , Ni)은 8.6 /s ∼ 1.3 /s, 음이온 핵종 (I, Tc)은 1.2 /s ∼ 9.5 /s, 악티나이드 핵종은 3.0 /s ∼ 1.8 /s 사이의 값을 나타내었다. 이때 확산계수는 모든 핵종에 대해 압축벤토나이트의 건조밀도가 증가할수록 감소하는 경향을 보였다.

본 연구에서는 수치실험을 통하여 규칙파의 주기와 파고를 변화시키면서 수리적 특성을 분석하였다. 수치해석에 사용한 모형의 지배방정식으로는 Navier-Stokes 방정식을 사용하였다. 또한, 자유수면의 변위를 정확하게 해석하기 위하여 VOF기법을 적용하였다. 수치모형실험을 통하여 수중방파제의 기울기 입사파의 주기와 파고 그리고 수중방파제의 유공율을 변화시키면서 월파유량 및 수리적 특성을 연구하였다. 연구결과 불투수성 수중방파제보다 투수성 수중방파제에서 월파유량을 더욱 저감시킴을 알 수 있었으며, 주기가 크고 파고가 클수록 월파유량이 증가함을 알 수 있었다.