지하 폐광도에 의한 지반침하 지역에서 전기비저항탐사와 시추공영상촬영을 통하여 지하공동의 분포 파악 및 지반 침하의 시간에 따른 변화량 측정을 수행하였다. 전기비저항탐사가 가능했던 연구지역 1에서는 100-150 ohm-meter 정도 낮은 비저항을 가지는 이상대가 관찰되었으며 시추조사와 시추공영상촬영 결과에서 폐갱도를 확인하였다. 연구지역 2는 도로로 피복되어 전기비저항탐사 수행이 불가능하였으나 광맥분포를 고려한 시추조사에서 채굴적 및 폐갱도를 확인하였다. 또한 시추공영상촬영을 43일간 총 6차례에 걸쳐 수행하여 시간에 따른 지하매질의 수직 이동 변위를 측정하였다. 지반침하로 인한 지하매질의 수직이동양상은 하부에서 상부보다 3배 이상 큰 규모로 발생하며 그 지속기간 역시 4배 이상 오랫동안 발생했음을 확인하였다. 효과적인 지하공동 탐지 및 지반침하 작용 모니터링을 위해서는 전기비저항탐사와 시추공영상촬영기법을 활용하는 것이 유용함을 알 수 있었다.

석회암 공동이 발달한 도심지역에서 지하수위 하강에 수반되어 발생한 함몰형 지반침하의 원인 규명 및 공동의 분포 특성 파악을 위하여 시추공을 이용한 전기비저항 토모그래피탐사를 실시하였다. 이때 지하수 수리지질 특성을 파악하기 위하여 시추코아의 비저항 측정, 지하수위 측정 및 수리전도도 해석을 병행하였다. 연구 지역에서의 완만한 지하수위 분포 특성과 0.8-9.3×10-4 cm/s 범위의 수리전도도 분포로 부터 연구지역의 수리지질 특성은 불균질성이 크지 않은 것으로 나타났다. 시추코아를 이용한 전기비저항 측정 결과 연구지역의 석회암은 파쇄가 많은 경우, 변질이 심한 경우 및 신선한 경우로 나눠지며, 전기비저항은 각각 103-161, 218-277 및 597-662 ohm-m의 범위로 나타났다. 시추결과 점토로 충전된 석회암 공동 지점은 토모그래피 탐사자료의 역산 결과 50 ohm-m 이하의 낮은 비저항으로 나타났으며, 각 시추공 간 비저항 영상 단면으로부터 연구지역 전체적으로 지표 하부 심도 약 10-20 m 구간까지 파쇄대 또는 석회암 공동 구간이 분포하는 것으로 나타났다. 또한 석회암 공동의 직경은 약 4-6 m 규모로, 대부분 점토질로 충전된 것으로 판단된다.

물리탐사와 시추자료에 대해 지구통계학적 복합해석 기술을 적용하여 3차원의 암반등급 해석을 수행하였다. 자료 복합 해석을 위한 다양한 지구통계학적 기술 중에서, 본 연구에서는 물리탐사 자료의 값을 추정하고자 하는 지점의 암반등급의 평균치로 치환하는 국소 변이 평균에 의한 단순 크리깅 기술(Simple Kriging with local varying means)을 사용하였다. 암석의 전기비저항 값은 RMR(Rock Mass Rating)값과 양의 상관관계를 갖는 것으로 알려져 있으나 상관 관계 만에 의한 대응방식은 그 양상이 매우 복잡하고 공간적으로 연관되어 있는 경우가 많아 단순히 적용하기 어려운 경우가 많다. 본 연구에서는 전기비저항과 RMR의 일반적 선형 상관관계 외에 지시자 변환(indicator transform)에 의한 비선형 상관관계를 유도하는 방식을 제안하였다. 또한 본 연구에서는 선형 및 비선형 상관관계에 의해 대응된 비저항 값이 실제 RMR과 비교할 때 나타나는 잔차(residual)에 대해 3차원 지구통계학적 분석을 적용하여 이 결과를 상관관계 결과에 추가함으로써 공간적 특성을 반영하는 RMR 평가를 수행할 수 있었다. 사용된 물리탐사 자료는 전기비저항 및 MT(Magnetotelluric) 탐사 자료이며, 총 10공의 시추자료를 통해 획득한 암반등급 값을 이용하였다. 이와 같은 해석은 조사 대상에 대한 광역적 지질조건을 보다 현실적으로 반영하는 암반등급 분포를 만들어내는 것으로 보인다.

표면파 탐사는 탄성파를 이용한 여러 가지 다른 탐사 방법과 비교하여 독특한 장점들을 가지고 있다. 그러나 이 방법은 최근에 개발되기 시작하여 아직 연구 결과가 많이 축적되지 않은 분야이다. 이 연구에서는 지반 공학적 성질이 서로 다를 것으로 예상되는 여러 지역에서 표면파 탐사자료를 획득하여 그 분산곡선의 특징을 찾아보았다. 또한 분산곡선을 역산하여 S파 속도구조를 구하여 이를 시추조사 결과와 비교하였다. 그 결과 퇴적물상이나 암석상의 변화가 S파속도의 급격한 변화와 관련되어 있음을 확인하였다. 이것은 표면파 탐사법을 이용하여 퇴적물이나 암석의 물리적 성질이 급격하게 변화하는 경계면을 구별할 수 있는 가능성을 시사한다.

유성일대 화강암, 팔당일대 호상 편마암 및 사북일대 퇴적암 지역에서 동탄성계수와 탄성파 속도와의 관계를 밝히기 위하여 완전파형음파검층을 통해 이들 암상에서 탄성파 P파와 S파 속도를 측정하였다. 또한 유성일대 화강암과 팔당일대 편마암 지역에 대해서는 일축압축강도와 포아송비를 실내시험에서 측정하였다. 실내실험 자료에서는 팔당 호상편마암 지역의 탄성파 P파 및 S파 속도가 유성의 화강암 지역보다 높게 나타난 반면, 포아송비가 낮은 값을 보이므로 포아송비의 증가함에 따라 탄성파 P파 및 S파 속도가 감소하는 상관관계를 보였다. 완전파형음파검층을 통하여 얻어진 동탄성계수는 동체적탄성계수와 동전단탄성계수에 비하여 높은 값을 보인다.

Temperature depth profiles measured in permafrost and western Utah generally represent anomalous curvatures. The accurate climate change can not be resolved with existing geothermal data, but general magnitude and timing explain the model of global warming. Differences between borehole temperatures observed in different intervals may concur with modeled temperature differences computed from the nearest air temperatures. This agreement indicates that boreholes are recording climate change.

We analyzed the mineral composition of compacted calcium bentonite (GJ-I) and uncompressed sodium bentonite (MX80), both of which were exposed for two years in the YS03 borehole. The YS03 borehole is characterized by a high concentration of anaerobic microorganisms, including sulfate-reducing bacteria, elevated levels of hydrogen sulfide, and high pH conditions. The compacted Ca bentonite showed minimal alteration, with a small amount of new magnetite formation. However, an X-ray diffraction (XRD) analysis revealed that the uncompressed Na bentonite underwent a complete transformation from montmorillonite to muscovite, goethite, and magnetite. Therefore, it is suspected that the compactness of the bentonite significantly impacts the rate of alteration. Furthermore, an X-ray fluorescence (XRF) analysis demonstrated a marked increase in iron oxide in the Na bentonite, whereas key elements of montmorillonite such as alumina (Al2O3), silica (SiO2), and magnesium oxide (MgO) showed substantial decreases. The presumed cause of the alteration in the uncompressed MX80 bentonite is the presence of Fe cations coupled with a high pH environment. We believe that Fe cations, which were likely released from the corrosion of cast iron, played a significant role in altering the montmorillonite lattice.

Deep borehole drilling is essential not only to select the host rock type for deep geological disposal of high-level radioactive waste (HLW), but also to identify the characteristics of the disposal site during the site selection process. In particular, since the disposal depth of HLW is considered to be over 300 m, deep borehole drilling must be performed. In deep borehole drilling, drilling design, excavation, and operation may vary depending on the rock type, drilling depth, and drilling purpose etc. This study introduced cases in which Korea was divided into four geotectonic structures and four representative rock types and conducted with a goal of 750 m drilling depth. Prior to this, a review of deep drilling cases conducted at domestic and abroad was presented. If sufficient time and cost are available, several drilling holes can be excavated for various purposes, but if not, one or two drilling holes should be used to achieve the objectives of various fields related to HLW disposal. The presence of bedding, strata or fault zones depending on the type of rock, etc. may affect drilling deviation or circulating water management. In addition, unlike drilling in general geotechnical investigation drilling, the use of polymers or grouting agents is limited to determine hydraulic and geochemical characteristics. This report introduces the experience considered during the design and drilling process of deep drilling in granite, gneiss, sedimentary rock, volcanic rock, etc., and is expected to be used as basic data when carrying out future HLW projects.

Despite the increasing interest in Deep Borehole Disposal (DBD) for its capability of minimizing disposal area, detailed research about DBD operation system design should be conducted before the DBD can be implemented. Recently, DBD operation system applying wireline emplacement (WE) technique is under study due to its high flexibility and capability of minimizing surface equipment. In this study, a conceptual WE system, and operation procdure is introduced. The conceptual WE system consists of 3 main stations, which from the top are hoisting station (HS), canister connection station (CCS) and basement (BS). In HS, WE is controlled and monitored. The WE is controlled using wireline drum winch and sheaves, and load on wireline is measured using a load cell. HS also has a pressure control system (PCS), which monitors internal pressure of the system, and a lubricator, which act as housing for joint device, allowing the joint device to be easily inserted into the borehole. The joint device is used to connect the disposal canister to wireline for emplacement/retrieval. In CCS, a rail transporter brings a transport cask containing disposal canisters, then the transport cask is connected to the hoisting system and a PCS in the BS. The main component located at canister station are a sliding shielding door (SSD), and a slip. The SSD is used to prevent canister from falling into borehole during the connecting operation and prevent radiation from BS to affect the workers. The slip is located beneath the SSD and is used to hold the disposal canister before it is lowered into the borehole. In BS, PCS is installed to prevent overflow and blowout of borehole fluid. The PCS consists of wireline pressure valve, christmas tree and BOP, which all are a type of pressure valve to seal the borehole and release pressure inside the borehole. The WE procedure starts with transporting transport cask to CCS. The transport cask is connected to lubricator, and PCS. Joint device is lowered down to be connected with disposal canisters, then pulled up to check the load on the wireline. After the check-up, SSD is opened, and disposal canister is lowered into the borehole. When desired depth is reached, joint device is disconnected and retrieved for next emplacement. In this study, the conceptual deep borehole disposal system design implementing WE technique is introduced. Based on this study, further detailed design could be derived in future, and feasibility could be tested.

The reliable information on the hydraulic characteristics of rock mass is one of the key site factors for design and construction of deep subsurface structures such as geological radioactive nuclear waste disposal repository, underground energy storage facility, underground research laboratory, etc. In order to avoid relying on foreign field test technology in future projects, we have independently designed and made integrated type main frame, 120 bar waterproof downhole sonde, and 1,200 m wireline cable winch through a series of R&D activities. They are core apparatuses of the Deep borehole Hydraulic Test System (DHTS). Integration of individual test equipment into a single main frame allows safe and efficient work in the harsh field condition. The DHTS was developed aiming primarily for constant pressure (head) injection test and pulse test in deep impermeable rock mass. The maximum testing depth of the DHTS is about 1,050 m from the surface. Using this system, it is possible to make precise stepwise control of downhole net injection pressure in less than 2.0 kgf/cm2 with dual hydraulic volume controller and also to inject and measure the very low flow rate below 0.01 l/min with micro flow rate injection/control module. Over the past two years, we have successfully completed more than 50 in situ hydraulic tests at 5 deep boreholes located in the Mesozoic granite and sedimentary rock regions in Korea. Among them, the deepest testing depth was more than 920 m. In this paper, the major characteristics of the DHTS are introduced and also some results obtained from the high precision field tests in the deep and low permeable rock mass environment are briefly discussed.

A GoldSim Total System Performance Assessment has been developed and utilized for assessment of the various conceptual HLW repositories for spent nuclear fuels during last a few decades. Even though, almost all required parameter values associated with the repository system are frequently assumed or sometimes overestimated, they are still far from being highly reliable. Uncertainties nested in nuclide transport modeling around the repository are mainly dominated by these parametric uncertainties aside from intrinsic model uncertainty. Reliable estimate of the parameter values commonly expressed as probability density functions (PDFs) always require a large amount of measured data. Such input distributions are used as input to the probabilistic assessment program through Monte Carlo simulation to quantitatively provide possible uncertainty of the results. However, in most cases, especially in the safety assessment of the repository which is typically related with both long-time span and wide modeling domain, inefficient observed data from the field measurements are common, making conventional probabilistic calculations rather even uncertain. Since Bayesian approach is known to be especially powerful and efficient in the case of lacking of available data measured, such short data could be compensated by coupling with a priori belief, reducing uncertainty. By allowing the a priori knowledge for incorporating insufficient observed data, which include expert’ elicitation, their beliefs and judgment regarding the parameters as well as recent site-specific measurements, based on the Bayes’ theorem, the older parameter distributions, “prior” distribution can be updated to a rather newer and reliable “posterior” distribution. Newer distributions are not necessarily expressed as PDFs for probabilistic calculation. These updates could be done even iteratively as many times as data values are sequentially available, which calls sequential Bayesian updating, making belief of posterior distributions become much higher by reducing parametric uncertainty. To show a possible way to enhance the belief as well as to reduce the uncertainty involved in parameter for the Bayesian scheme, nuclide travel length in the far-field area of a hypothetical deep borehole spent fuel Repository was investigated. The algorithm and module that have been developed and implemented in GSTSPA through current study was shown to work well for all assumed prior, three sequential posterior distributions and likelihoods.

Deep geological disposal (DGD) of spent nuclear fuels (SNF) at 500 m–1 km depth has been the mainly researched as SNF disposal method, but with the recent drilling technology development, interest in deep borehole disposal (DBD) at 5 km depth is increasing. In DBD, up to 40SNF canisters are disposed of in a borehole with a diameter of about 50 cm, and SNF is disposed of at a depth of 2–5 km underground. DBD has the advantage of minimizing the disposal area and safely isolating highlevel waste from the ecosystem. Recently, due to an increasing necessity of developing an efficient alternative disposal system compared to DGD domestically, technological development for DBD has begun. In this paper, the research status of canister operation technology and plans for DBD demonstration tests, which subjects are being studied in the project of developing a safety-enhancing high-efficiency disposal system, are introduced. The canister operation technology for DBD can be divided into connection device development and operation technology. The developing connection device, emplacing and retrieving canisters in borehole, adopted the concept of a wedge thus making replacement equipment at the surface unnecessary. The new connection device has the advantage of being well applied with emplacement facilities only by simple mechanical operation. The technology of operating a connection device in DBD can be divided into drill pipe, coiled tubing, free-drop, and wireline. The drill pipe is a proven method in the oil industry, but requiring huge surface equipment. The coiled tubing method uses a flexible tube and shares disadvantages as the drill pipe. The free-drop is a convenient method of dropping canister into a borehole, but has a weakness in irretrievability in an accident. Finally, the wireline method can be operational on a small scale using hydraulic cranes, but the number of operated canisters at once is limited. The test facility through which the connection device is to be tested consists of dummy canister, borehole, lifting part, monitoring part, and connecting device. The canister weight is determined according to the emplacement operation unit. The lifting part will be composed following wireline consisting of a crane, a wire and a winding system. The monitoring part will consist of an external monitoring system for hoists and trolleys, and an internal monitoring system for the connection device’s location, pressure, and speed. In this project, a demonstration test will be conducted in a borehole with 1km depth, 10 cm diameter provided by KAERI to verify operation in the actual drilling environment after design improvement of the connecting device. If a problem is found through the demonstration test, the problem will be improved, and an improved connection device will be tested to an extended borehole with a 2 km depth, 40 cm diameter.

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.