본 연구는 초등학교 학습자들의 지질학적 시간 개념 인식에 따라 퇴적암 형성 과정을 어떻게 이해하고 있는지를 알아보기 위한 연구이다. 연구의 실행은 B 광역시에 위치한 U 초등학교 4학년 학생 57명을 최종 분석의 대상으로 진행되었으며, 데이터의 수집은 Jolley et al. (2012)이 개발한 LIFT (The Landscape Identification and Formation Test) 검사 도구를 수정 및 번안하여 객관식 문항을 구성하고, Charles and McConnell (2018)이 활용한 지질학적 경관 형성에 대한 인터뷰의 구조를 서술식 문항으로 제작하여 데이터를 수집하였다. 서술형 문항 응답 결과를 질적으로 분석하여 학생들의 지질학적 시간 개념 표출 유형을 기준으로 세 군집으로 분류하였다. 분류된 군집은 각각 구체적 시간 개념 군집(Specific time concept cluster), 막연한 시간 개념 군집(Vague time concept cluster), 시간 개념 미표현 군집(No time concept cluster)으로 명명되었으며, 각 군집별로 퇴적암 형성 과정에 대한 단답형 문항의 점수를 활용하여 통계적 검증을 수행하 였으며, “구체적 시간 개념” 군집은 “시간 개념 미표현” 군집에 비해 퇴적암 형성 과정에 대한 이해가 통계적으로 유의 미하게 높은 것을 확인하였다. 또한 그 구체적 사례에서 Ault (1982)가 언급한 지질학적 연대에 대한 과소 추정과 과대 추정의 사례를 발견하였다. 또한 각 군집별로 수집된 서술형 문항(퇴적암 형성 과정에 대한 서술)을 바탕으로 언어 네트 워크를 형성하고, 중심도 분석을 실시하여 시각화한 후 분석하였다. 분석 결과, 구체적 시간 개념 군집은 퇴적암 형성의 모든 과정에 대해 비교적 잘 인식하고 있으며, 지질학적 시간 개념이 현상과 잘 연결되어 있는 것을 확인하였다. 또한, 막연한 시간 개념 군집은 퇴적암 형성 과정에서 퇴적, 압축, 교결, 암석화, 노출의 과정이 비교적 잘 연결되어 있지 않지 만, 지질학적 시간 개념은 비교적 잘 인식하고 있었으며, 시간 개념 미표현 군집은 퇴적암 형성 과정에서 퇴적, 압축, 교 결 작용을 중심으로 설명하고 있으며, 지질학적 시간 개념의 인식 또한 거의 이루어지지 못하고 있다는 것을 확인하였 다. 추가로, 각 군집별 시간 노드의 커뮤니티가 가지는 중심도를 활용해 커뮤니티 분석을 실시간 결과, “시간 개념 미표 현” 군집은 퇴적암의 형성 과정을 시간 개념과 연관시키는 것에 어려움을 겪는 것을 확인하였다.

강으로부터 해양으로 유입되는 퇴적물은 유역분지의 지질, 지리, 지형, 기후 등의 영향을 반영하며, 육상 유역분 지에서 퇴적물 생성 과정에서 수반되는 화학적 풍화는 대기 중 이산화탄소 농도를 조절하는 데에 중요한 역할을 하는 것으로 알려져 있다. 본 연구에서는 한반도 남해안 낙동강 하구 인근 해저 표층 퇴적물의 지화학 조성을 이용하여 화 학적 풍화의 강도와 퇴적물의 기원지에 분포하는 암석의 조성을 추정하였다. 연구 시료의 화학적 풍화 강도는 중간에 낮은 정도(평균 Chemical Index of Alteration=68)이며 A-CN-K 도표에서 추정한 풍화의 추세는 퇴적물의 기원지 성분 이 평균적인 상부 대륙지각과 매우 유사한 것으로 보인다. 이는 낙동강 유역분지에 분포하는 중생대 화강암류와 경상누 층군 퇴적암이 혼합된 성분을 반영하는 것으로 판단되기 때문에 연구 대상인 퇴적물이 낙동강 하구로부터 유입되는 퇴 적물의 성분을 대표하는 것으로 해석한다. 표층 퇴적물의 희토류원소는 분화된 경희토류-중희토류의 비와 음의 Eu 이상 을 나타내어 상부 대륙지각과 매우 유사하다. 본 연구의 결과를 전 세계 강 하구 퇴적물 자료 및 국내의 큰 강 자료와 비교하였으며, 이를 통하여 지질 및 지형의 잠재적인 영향을 고려할 수 있다.

The increasing accumulation of spent nuclear fuel has raised interest in High-Level Waste (HLW) repositories. For example, Sweden is under construction of the KBS-3 repository. To ensure the safety of such HLW repository, various countries have been developing assessment models. In the Republic of Korea, the Korea Atomic Energy Research Institute has been developing on the AKRS model. However, traditional safety assessment models have not considered the fracture growth in the far-field host rock as a function of time. As repository safety assessments guarantee safety for million years, sustained stress naturally leads to the progressive growth of fractures as time goes on. Therefore, it becomes essential to account for fracture growth in the surrounding host rock. To address this, our study proposes a new coupling scheme between the Fracture growth model and the radionuclide transport model. That coupling scheme consists of the Cubic Law model as a fracture growth function and the GoldSim code which is a commercial software for radionuclide transport calculations. The model that adopting such fracture growth functions showed an increase of up to 15% in the release of radionuclide compared to traditional assessment models. our observations indicated that crack growth as a function of time led to an increase in hydraulic conductivity that allowed more radionuclide transport. Notably, these findings show the significance of adopting fracture growth models as a critical element in evaluating the safety of nuclear waste repositories.

Rock discontinuities in underground rock behave as weak planes and affect the safety of underground structures, such as high-level radioactive waste disposal and underground research facilities. In particular, rock discontinuities can be a main flow path of groundwater and induce large deformation caused by stress disturbance or earthquakes. Therefore, it is essential to investigate the characteristics of rock discontinuities considering in-situ conditions when constructing highlevel radioactive waste disposal, which needs to assure the long-term safety of the structure. We prepared Hwang-Deung granite rock block specimens, including a saw-cut rock surface, to perform multi-stage direct shear tests as a preliminary study. In the multi-stage direct shear tests, we can exclude possible errors induced by different specimens for obtaining a full failure envelope by using an identical specimen. We applied the initial normal stress of 3 MPa on the specimen and increased the normal stress to 5 and 10 MPa step by step after peak shear stress observation. We obtained the mechanical properties of saw-cut rock surfaces from the experiments, including friction coefficient and cohesion. Additionally, we investigated the effect of filling material between rock discontinuities, assuming the erosion and piping phenomenon in the buffer material of the engineering barrier system. When the filling material existed in the rock surfaces, the shear characteristics deteriorated, and the effect of bentonite was dominant on the shear behavior.

Compacted bentonite buffer blocks placed in the engineered barrier system for high-level nuclear waste disposal can undergo swelling, intrusion into rock fractures, and erosion with saturation. Bentonite erosion and intrusion can lead to bentonite mass loss via groundwater flow and can ultimately compromise the overall integrity of the disposal system. To ensure the long-term safety of deep geological disposal, it is essential to assess the hydro-mechanical interactions between the bentonite buffer and surrounding rock. In this study, the impact of bentonite erosion and intrusion on the mechanical properties of the jointed rock mass were assessed via elastic wave propagation measurements using the quasi-static resonant column test. Granite rock discs obtained from the Korea Underground Research Tunnel and Gyeongju bentonite were used to simulate jointed rock specimens with different bentonite intrusion conditions. Different degrees of bentonite intrusion were simulated by mixing bentonite and water to create bentonite paste and gel. The longitudinal and shear wave velocities under different normal stress levels were used to quantify the effects of bentonite intrusion on the mechanical characteristics of the rock joint. Complementary numerical analysis using the three-dimensional distinct element code (3DEC) was conducted to provide improved understanding of wave propagation within bentonite gouge-filled rock mass.

Coupled thermo-hydraulic-mechanical (THM) processes are essential for the long-term performance of deep geological disposal of high-level radioactive waste. In this study, a numerical sensitivity analysis was performed to analyze the effect of rock properties on THM responses after the execution of the heater test at the Kamaishi mine in Japan. The TOUGHFLAC simulator was applied for the numerical simulation assuming a continuum model for coupled THM analysis. The rock properties included in the sensitivity study were the Young’s modulus, permeability, thermal conductivity, and thermal expansion coefficients of crystalline rock, rock salt, and clay. The responses, i.e., temperature, water content, displacement, and stress, were measured at monitoring points in the buffer and near-field rock mass during the simulations. The thermal conductivity had an overarching impact on THM responses. The influence of Young’s modulus was evident in the mechanical behavior, whereas that of permeability was noticed through the change in the temperature and water content. The difference in the THM responses of the three rock type models implies the importance of the appropriate characterization of rock mass properties with regard to the performance assessment of the deep geological disposal of high-level radioactive waste.

Radionuclides can be leached into groundwater or soil over a long period of time due to unexpected situations even after being permanently disposed of in a repository. Therefore, it is necessary to investigate the mobility of radionuclides for the safety assessment of radioactive waste disposal. In this study, the effects of organic complexing agents such as ethylenediaminetetraacetic acid (EDTA) and isosaccharinic acid (ISA) on the sorption behavior of 239Pu and 99Tc over cementitious (concrete and grout) and natural rock samples (granite and sedimentary rock) were investigated in batch sorption experiments. For characterization of rock samples, XRD, XRF, FT-IR, FE-SEM, BET, and Zeta-potential analyses were performed. For the evaluation of mobility, the distribution coefficient (Kd) was selected and compared. The adsorption experiment was carried out at two pHs (7 and 13), a temperature of 20°C, and a range of organic complexing agents concentrations (10-7~10-2 M and 10- 5~10-2 M for 239Pu and 99Tc, respectively). The radionuclides concentrations in adsorption samples were analyzed using ICP-MS. The Kd values for 239Pu in all rock samples reduced significantly due to the presence of EDTA, even at low concentrations such as 10-5 M. In the case of ISA, the limiting noeffect concentration was much higher than that of EDTA. On the other hand, 99Tc showed relatively lower Kd values than 239Pu, and the sorption behavior of 99Tc was almost unaffected by the organic complexing agents for all rock samples. Therefore, it is possible to assume that the increased mobility of radionuclides, especially, 239Pu, in groundwater caused by the lowering of sorption at even low concentrations of organic complexing agents may result in the transport of radionuclides to the nearand far-field location of the repository.

In high-level radioactive waste disposal, a high temperature is generated from the canister containing the waste in the engineered barrier, while groundwater flows into the buffer system from the host rock. The temperature increase and groundwater inflow result in the water phase change and saturation variation. Saturation change is related to the thermal conductivity of buffer material; hence the phase change and saturation strongly interact with the temperature evolution. The complex coupled behavior affects the stability of the whole disposal system, and the security of the repository is critical to human-being life. However, it is difficult to predict the long-term coupled behavior in the disposal system due to the considerable field-test scale, and therefore a numerical simulation is a suitable method having repeatability and cost-effectiveness. DECOVALEX is an international cooperating project for developing numerical methods and models for thermo-hydro-mechanical-chemical (THMC) interaction. DECOVALEX has a four-year cycle with various topics. At the current phase, Task C aims to simulate the full-scale emplacement (FE) experiment performed at Mont Terri underground rock laboratory. Nine research groups are participating in the task, and among them, KAERI simulates the experiment using OGS-FLAC. The simulator combines OpenGeoSys for TH simulation and FLAC3D for M simulation. Through the benchmark simulation, we verified OGS-FLAC for the two-phase flow analysis in the disposal system and finally modeled the FE experiment with a three-dimensional grid. We performed a simple sensitivity analysis to investigate the effect of input parameters on the two-phase flow system and confirmed that the compressibility and permeability affected the flow behavior. We also compared the simulation results to the field data and obtained well-matched results from a series of simulation.

Low to intermediate radioactive waste disposal concrete structures are subjected to coupled hydromechanical conditions and the identification of structural damage is crucial to ensure safe long-term disposal. Different damage models for concrete and the surrounding rock can affect the damage characteristics of radioactive waste disposal structures. In this study, the effects of different rock damage models are applied to the hydro-mechanical-damage coupled structural analysis of the Wolseong Low and Intermediate Level Radioactive Waste Disposal Center silo. A two-dimensional model of the disposal silo was modeled using the finite element analysis software COMSOL and the Mazars’ damage model was applied to the silo concrete. The Mazars’ model parameters were obtained from uniaxial compression and tensile tests on cylindrical concrete specimens after 28 days of water curing and further 32 days of wet curing at 75°C). The COMSOL embedded Richards equation module was used to simulate hydraulic analysis. Structural loading due to waste disposal was applied at the bottom of the silo structure and the damage evolution characteristics were investigated. The non-linear mechanical rock behavior obtained from laboratory tests (Hoek-Brown criterion, resonant column test, Mazar’s damage model) and field tests (Goodman Jack) were input to assess the effects of different rock damage models. The results highlight the importance of structural damage consideration when assessing the long-term stability and safety of underground radioactive waste disposal structures under coupled hydro-mechanical conditions.

The design of the high-level radioactive waste (HLW) repository is made for isolating the HLW from the groundwater system by using artificial and natural barriers. Granite is usually considered to be a great natural barrier for the HLW repository in various countries including Sweden, Canada, and Korea due to its low hydraulic permeability. However, many fractures that can act as conduits for groundwater and radionuclides exist in granite. Furthermore, the decay heat generated by the HLW can induce groundwater acceleration through the fracture. Since the direction, magnitude, and lasting time of the heat-induced groundwater flow can be differed depending on the fracture geometry, the effect of fracture geometry on the groundwater flow around the repository should be carefully analyzed. In this study, groundwater models were conducted with various fracture geometries to quantify the effect of various properties of fractures (or fracture networks) on the heat-induced groundwater flow. In all models, the pressure around the repository only lasted for a short period after it peaked at 0.1 years. In contrast, the temperature lasted for 10,000 years after the disposal inducing the convective groundwater flow. Single fracture models with different orientations were conducted to evaluate the variations in groundwater velocities around the repository depending on the fracture slope. According to the results, the groundwater velocity on the fracture was the fastest when the regional groundwater flow direction and the fracture direction coincided. In double fracture models, various inclined fractures were added to the horizontal fracture. Due to the intersecting, the groundwater flow velocity showed a discontinuous change at the intersecting point. Lastly, the discrete fracture network models were conducted with different fracture densities, length distributions, and orientations. According to the modeling results, the groundwater flow was significantly accelerated when the fracture network density increased, or the average fracture length increased. However, the effect of the fracture orientation was not significant compared to the other two network properties.

이 연구는 국토지리정보원, 국립해양조사원, 한국국토정보공사 등 관계기관에서 제작된 독도지도에 독도의 부속도서 수가 상이하게 표현되고 있는 문제로부터 시작되었다. 따라서 이 연구는 독도에 지번이 처음으로 부여되었던 시점부터 현재까지 관계기관 및 민간지도제작사에서 제작된 독도지도를 분석함으로써 문제의 원인을 찾아내고, 정책적 제언을 하는 것이 목적이다. 연구결과, 첫째, 독도 주변에 분포하는 바위섬이나 암초들을 부속도서로 통칭하는 것은 무리가 있는 것으로 판단된다. 관계기관에서는 바위섬과 암초를 명확하게 구분하고, 부속도서라는 명칭을 계속해서 쓸 것인지, 또는 선별적으로 쓸 것인지 여부를 논의할 필요가 있다. 둘째, 독도의 산정부에서 떨어진 암석 덩어리까지 부속섬으로 집계되는 경우도 있는데, 이는 현지조사가 제대로 이루어지지 않은 문제라 사료된다. 따라서 관계기관에서는 독도 주변의 바위섬과 암초의 분포를 명확하게 파악한 후 지도화 작업을 해야 할 것이다. 끝으로, 바위섬과 암초에 부여된 지번을 계속 유지할 것인지 여부를 심도있게 논의할 필요가 있다. 규모가 작은 바위섬이나 암초의 경우는 풍화작용이나 파식작용에 의해 언제든지 사라질 수도 있기 때문에 이들 부속섬에 지번을 부여하는 문제는 신중할 필요가 있다.

본 연구의 목적은 암석 판별 탐구에서 중학교 영재학생들의 과학적 관찰과 추론의 특징을 탐색하기 위함이었다. 이를 위하여 영재교육원에 다니는 19명의 중학교 1학년 학생들에게 과학 교과서에서 중요하게 다루는 화성암, 변성암, 퇴적암이 포함된 5가지 암석 샘플을 나누어 주고 각 암석의 형성과정, 종류, 이름 등을 유추해 보도록 하였다. 연구 결과, 학생들이 주로 주목하는 암석의 특징은 색, 조직, 구조로 나타났다. 전형적인 암석의 경우 기억에 의존하여 즉각적으로 암석 판별에 성공하나 관찰에 근거한 유의미한 추론이 이루어지지 못하는 반면, 판별에 어려움을 겪는 암석의 경우 관찰에 근거한 유의미한 추론 과정이 담화를 통해 드러나기도 하였다. 또한 유의미한 관찰 결과로부터 과학적 추론 을 타당하게 구성하였으나 암석 판별에 실패한 경우도 나타났다. 본 연구 결과는 중학생들의 암석 판별 탐구 활동에서 학생들의 현 수준을 파악하고, 학교 현장에서 이루어지는 암석 판별 탐구가 학생들에게 과학적 관찰과 추론의 경험을 제공할 수 있도록 방안을 모색하고, 시사점을 제공하고자 한다.