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.

A disposal system for spent nuclear fuel mainly divides into two parts; Engineered barriers include spent nuclear fuel, canister, buffer and backfill and natural barriers mean a host rock surrounding engineered barriers. If radionuclides released from a repository, they can migrate to the ecosystem. Sorption plays an important role in retarding the migration of released radionuclides. Hence, the safety assessment for the disposal of a spent nuclear fuel should consider the migration and retardation of radionuclides in geosphere. Distribution coefficient is one of input parameters for the safety assessment. In this work, distribution coefficients for crystalline rock as a natural barrier were collected and evaluated for the purpose of safety assessment for the deep geological disposal of a spent nuclear fuel. The radionuclides considered in this work are as follows; alkali and alkaline earth metals (Cs, Sr, Ba), lanthanides (Sm), actinides (Ac, Am, Cm, Np, Pa, Pu, Th U), transition elements (Nb, Ni, Pd, Tc, Zr), and others (C, Cl, I, Rn, Se, Sn). The sorption of radionuclides is influenced by various geochemical conditions such as pH/carbonates, redox potential, ionic strength, radionuclide concentration, kinds and amounts of minerals, and microbes. For the evaluation of distribution coefficients, the data from Sweden (SKB), Finland (Posiva), Switzerland (Nagra), and Japan (JAEA) were collected, analyzed, and the recommended distribution coefficients have been suggested.

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.

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.

Discontinuities exert great influence on the thermal, hydraulic, and mechanical behavior of rock mass. Rock joint is one of the most frequently encountered discontinuities in many engineering applications, such as tunnel, rock slope and repository for high level radioactive waste. Therefore, the effects of rock joint should be thoroughly investigated in various aspects. Rock joint has gone through many geological processes and its behavior can be characterized by many properties. Among them, geometric properties, such as joint roughness, aperture, and contact area can affect mechanical and hydraulic properties and vice versa. Therefore, accurate understanding and characterization of the geometric properties are of importance. Generally, the geometric properties of a joint are obtained or estimated using the surface height or elevation, which could be measured by various contact or noncontact methods. Then, the coordinates of the surfaces are used to calculate several parameters, for instance roughness indexes and mechanical aperture, in a quantitative manner. This paper is a part of SKB task force project that aims to evaluate the geometric properties of rock joints and to analyze the hydromechanical behavior within a rough joint considering the properties. Four pairs of joint surfaces were laser-scanned in order to obtain coordinates of the surfaces and then the coordinates were used to calculate the roughness, directional roughness, aperture, and spatial correlations. At the same time, fluid flow within a rough joint were simulated by a commercial FEM code, considering the variation of aperture space due to normal load. Flowrate, flow path, and channelization were investigated in an aperture scale. Since rock mass consists of several joints and/or joint sets, characterization of a single rock joint can be utilized for analyzing the behavior of rock mass as a reference.

With the increasing demand for a repository to safely dispose of high-level radioactive waste (HLW), it is imperative to conduct a safety assessment for HLW disposal facilities for ensuring the permanent isolation of radionuclides. For this purpose, the Korea Atomic Energy Research Institute (KAERI) is currently developing the Adaptive Process-based total system performance assessment framework for a geological disposal system (APro). A far-field module, which specifically focuses on fluid flow and radionuclide transport in the host rock, is one of several modules comprising APro. In Korea, crystalline rock is considered the host rock for deep geological disposal facilities due to its high thermal conductivity and extremely low permeability. However, the presence of complex fracture system in crystalline rock poses a significant challenge for managing fluid flow and nuclide transport. To address this challenge, KAERI is participating in DECOVALEX-2023 Task F1, which seeks to compare and verify modeling results using various levels of performance assessment models developed by each country for reference disposal systems. Through the benchmark problems suggested by DECOVALEX-2023 Task F1, KAERI adopts the Discrete Fracture-Matrix (DFM) as the primary fracture modeling approach. In this study, the transport processes of reactive tracers in fractured rock, modeled with DFM, are simulated. Specifically, three different tracers (conservative, decaying, adsorbing) are introduced through the fracture under identical injecting conditions. Thereafter, the breakthrough curves of each tracer are compared to observe the impact of reactive tracers on nuclide transport. The results of this study will contribute to a better understanding of nuclide behavior in subsurface fractured rock under various conditions.

In KAERI, a site descriptive model for stress field estimation had already been constructed by using integrated field data within KURT site scale. A sub-divided rock block domain containing major fracture zones has spatial rock mass and fault properties. The properties were decided based on the rock classification results of several borehole investigations. Modeling for maximum and minimum horizontal stress field estimation was performed and compared with the in-situ data. As a result, a depth-dependent stress ratio was adopted to obtain numerical results closer to actual in-situ data. Although the results were suitable at a relatively low depth (~500 m), there is still some deviation trend at a deep depth. This study aims to improve these modeling results by incorporating not only depth-dependent stress ratio but also changes in rock mass properties along the depth. The deep borehole of DB2 in the KURT site indicated fracture distribution corresponding to the property changes. Natural fractures are typically randomly oriented, and the fracture frequency decreases with increasing depth. The increase in P-wave velocity log data accompanies these features. A discrete fracture network (DFN) model can be used to simulate fractured rock explicitly, but DFN modeling is not feasible for site scale analysis because of its numerical efficiency. Therefore, as a preliminary model in this study, the effect of fracture distribution was considered by substituting the influence for the depth-dependent property. The properties were estimated from the fracture frequency and P-wave velocity log data. The influence of elastic modulus and density on the site stress field was dominant, with decreasing the deviation trend between modeling and in-situ data at a deep depth. Considering that the depth of the repository construction is within about 500 m, it may not be necessary to consider the change of rock properties with depth. However, it was determined that the rock property effect might need to be considered when the loading conditions change due to subsidence in the long-term evolution scenario. Continuously, this site descriptive modeling will be interdependently conducted with a representative DFN block model for deriving equivalent properties in fractured rock.

The acoustic emission (AE) method as a passive non-destructive monitoring technique is proposed for real-time monitoring of mechanical degradation in underground structures, such as deep geological disposal of high-level nuclear waste (HLW). This study investigates the low-frequency characteristics of AE signals emitted during the fracturing of meter-scale concrete specimens; uniaxial compression tests (UCT) in a lab scale and Goodman jack (GJ) tests in a 1.3 m-long concrete block were conducted while acquiring the AE signals using low-frequency AE sensors. The results indicate a sharp increase in AE energy emission at approximately 60% and 80% of the yield stresses in the UCT and GJ tests, respectively. The collected AE signals were primarily found in two frequency bands: the 4-28 kHz range and the 56-80 kHz range. High-frequency AE signals were captured more as the stress increased in the GJ tests, which was in contrast to the UCT tests. Furthermore, the AE signals obtained from the Goodman jack tests tended to lower RA values than the UCT results. This study presents unique experimental data with low-frequency AE sensors under different loading conditions, which provides insights into field-scale AE monitoring practices.

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.

이 연구의 목적은 지구과학 교사들이 변성암을 분류하기 위해 사용하는 개념 구조와 변성암을 분류하는 기준에 대해 알아보는 것이다. 이를 위해 연구자들은 전라북도 소재의 중학교와 고등학교의 지구과학교사 21명을 대상으로 사 고 구술을 활용하여 변성암을 분류하는 과정에서 진술한 언어 자료를 수집하였다. 그리고 이렇게 수집된 언어 자료를 언어네트워크분석법을 활용하여 분석하였고, 그 결과는 다음과 같다. 첫째, 지구과학 교사들은 변성암을 분류하는 과정 에서 암석에서 일반적으로 관찰할 수 있는 색, 구성 광물, 입자의 크기 등의 특징과 변성암에서 나타나는 엽리를 중심 으로 분류하였다. 둘째, 지구과학 교사들은 변성암의 분류 기준에 관해 접촉 변성작용과 광역 변성작용 등 변성작용을 중심으로 인식하고 있었다. 그러나 관찰한 내용을 잘못 판단하여 다른 암석으로 오인하는 사례들이 나타났다. 그러므로 지구과학 교사들이 변성암이 형성되는 과학적 과정과 변성암에서 관찰되는 현상을 서로 연결하여 인식할 수 있도록 그 들에게 변성암에 대한 관찰 정보와 경험을 충분히 제공할 필요가 있다.

Barnea manilensis is a bivalve which bores soft rocks, such as, limestone or mudstone in the low intertidal zone. They make burrows which have narrow entrances and wide interiors and live in these burrows for a lifetime. In this study, the morphology and the microstructure of the valve of rock-boring clam B. manilensis were observed using a stereoscopic microscope and FE-SEM, respectively. The chemical composition of specific part of the valve was assessed by energy dispersive X-ray spectroscopy (EDS) analysis. 3D modeling and structural dynamic analysis were used to simulate the boring behavior of B. manilensis. Microscopy results showed that the valve was asymmetric with plow-like spikes which were located on the anterior surface of the valve and were distributed in a specific direction. The anterior parts of the valve were thicker than the posterior parts. EDS results indicated that the valve mainly consisted of calcium carbonate, while metal elements, such as, Al, Si, Mn, Fe, and Mg were detected on the outer surface of the anterior spikes. It was assumed that the metal elements increased the strength of the valve, thus helping the B. manilensis to bore sediment. The simulation showed that spikes located on the anterior part of the valve received a load at all angles. It was suggested that the anterior part of the shell received the load while drilling rocks. The boring mechanism using the amorphous valve of B. manilensis is expected to be used as basic data to devise an efficient drilling mechanism.