Review on the Geochemical Effects on the Coupled Processes of Discontinuous Natural Barrier System

Saeha Kwon,Changsoo Lee,Jin-Seop Kim 한국방사성폐기물학회 2023 한국방사성폐기물학회 학술논문요약집 Vol.21 No.2

The natural barrier system surrounding the geological repository for high-level radioactive waste plays a crucial role in preventing or delaying the leakage of radionuclides. Therefore, the natural barrier should ensure low permeability to prevent groundwater flow into the engineered barrier system throughout the repository’s lifetime. Crystalline rock, considered as the host rock for the geological repository in Korea, exhibits low intact rock permeability, but the crystalline rock often contains the multiple discontinuities due to its high brittleness that can allow the unexpected fluid flow. Therefore, the long-term hydraulic behavior of the discontinuity should be characterized while considering additional thermal, mechanical, and chemical effects. In comparison to thermal, hydraulic, and mechanical processes, the chemical processes on the discontinuities progress relatively slowly, resulting in limited researches to include these chemical processes. This research introduces mechanisms the involving coupled thermal-hydraulic-mechanicalchemical processes focusing on the rough fracture surfaces and asperities. The chemically-induced changes in mechanical and hydraulic properties are described based on pressure solution and precipitation concepts. A comprehensive review of laboratory tests, field tests, and numerical simulations is conducted related to the chemically-induced coupled processes in fractured rock. Laboratory tests, in particular, concentrate on microscopic changes in fracture asperities induced by pressure solution to analyze chemically-induced aperture changes. The TOUGHREACT, an integral finite difference method program for thermal-hydraulic-chemical simulations, is generally employed to model the chemical response of pressure solution and precipitation on fracture surfaces. The TOUGHREACT includes a module to describe effective porosity and permeability changes based on the modified cubic law, so the real-time change of the fracture permeability can be reflected during the flow simulation. Considering the coupled thermal-hydraulic-mechanicalchemical processes of discontinuity, it becomes evident that the chemical processes under repository conditions (long-term, high temperature, and high pressure) can disturb the hydraulic performance of the natural barrier, so further research is required to characterize the chemically-induced coupled processes for assessing the long-term performance of the natural barrier system.

Characterization of 4.2-km-Deep Fractured Granodiorite Cores from Pohang Geothermal Reservoir, Korea

Kwon, Saeha,Xie, Linmao,Park, Sehyeok,Kim, Kwang-Il,Min, Ki-Bok,Kim, Kwang Yeom,Zhuang, Li,Choi, Jaiwon,Kim, Hanna,Lee, Tae Jong Springer-Verlag 2019 Rock mechanics and rock engineering Vol.52 No.3

Numerical Analysis of the Barcelona Basic Model by the Discontinuum -Based Metho

Saeha Kwon,Changsoo Lee,Jin-Seop Kim 한국방사성폐기물학회 2023 한국방사성폐기물학회 학술논문요약집 Vol.21 No.2

The Barcelona Basic Model (BBM) is an elasto-plastic model used to describe the coupled thermo-hydro-mechanical behaviors of unsaturated soil. BBM is frequently adopted to model the unique swelling behavior of bentonite, which is generally considered as the buffer material between the host rock and the canister containing high-level radioactive waste in deep geological repositories, under the changing thermal, hydraulic, mechanical and chemical conditions during the lifetime of repository. Therefore, a variety of the continuum-based numerical methods tried to add the BBM for modelling the multi barrier systems of geological repository and succeeded to describe the elasto-plastic deformation of bentonite. However, to demonstrate the entire barrier systems the host rock should be modelled simultaneously with the buffer materials, and the continuum-based methods may be limited in their ability to reflect the fracture networks in the host rock which could be the major flow channels of groundwater. This research applies BBM in 3DEC, a three-dimensional block-based discrete element method, and validates the model by comparing the change of specific volume and mean effective stress during three numerical test cases. Discontinuum-based numerical methods with BBM can be extended to describe the coupled thermo-hydro-mechanical processes of multi-barrier systems in geological repositories, with a focus on the interaction between the host rock and bentonite.

Numerical Comparisons for Assessing the Thermo-hydro-mechanical Simulation Performance of TOUGH-3DEC

Saeha Kwon,Kwang-Il Kim,Changsoo Lee,Jin-Seop Kim 한국방사성폐기물학회 2022 한국방사성폐기물학회 학술논문요약집 Vol.20 No.1

Discontinuum-based numerical methods can contain the multiple discontinuities in a model and reflect the thermal, hydraulic and mechanical characteristics of discontinuities. Therefore, discontinuum methods can be appropriate to simulate the model which require the detailed analysis of the coupled thermo-hydro-mechanical processes in fractured rock such as geothermal energy, CO2 geo-sequestration, and geological repository of the high-level radioactive waste. TOUGH-3DEC, the three-dimensional discontinuum simulators for the coupled thermo-hydro-mechanical analysis, was developed by linking the integral finite difference method TOUGH2 and the explicit distinct element method 3DEC to describe the coupled thermo-hydro-mechanical processes in both porous media and discontinuity. TOUGH2 handles thermo-hydraulic analysis by the internal simulation module, and 3DEC performs mechanical study based on the constitutive models of porous media and discontinuity with coupling the thermal and hydraulic response from TOUGH2. The thermal and hydraulic couplings are the key processes and should be carefully verified by sufficient cases, so this study performed the thermomechanical and hydro-mechanical simulations which are modelling the analytic solutions including the uniaxial consolidation, fracture static opening, and the heating of a hollow cylinder problems. Each thermo-mechanical and hydro-mechanical verification case is also validated by comparing with the results of the other continuum and discontinuum-based numerical methods. TOUGH-3DEC results follow the analytic solutions and show better accuracy than the continuum-based numerical methods in the static fracture opening problem. The developed TOUGH-3DEC simulator can be expanded to coupled thermo-hydro-mechanical-chemical analysis in fractured rock mass, and the simulator needs to be verified by more complicated coupled processes problems which require in the chemical coupling.

Development of the Three-dimensional Discontinuum-based Coupled Hydromechanical Simulator for Modelling a Deep Geological Repository

Saeha Kwon,Kwang-Il Kim,Changsoo Lee,Jin-Seop Kim 한국방사성폐기물학회 2021 한국방사성폐기물학회 학술논문요약집 Vol.2021 No.11

스웨덴 포쉬마크 중저준위 방사성 폐기물 지하 처분장 확장 계획 소개

권새하(Saeha Kwon),민기복(Ki-Bok Min),우베 스테판손(Ove Stephansson) 한국암반공학회 2016 터널과지하공간 Vol.26 No.5

스웨덴 포쉬마크 (Forsmark)지역에서는 1988년부터 세계 최초의 동굴식 중저준위 방사성 폐기물 처분장(SFR1)이 운영되고 있다. 4개의 터널 및 1개의 사일로에 용량 63,000 ㎥의 처분공간이 확보되어 연간 1,000 ㎥의 폐기물을 처분할 수 있었지만, 스웨덴 내 12기 중 10기의 원자로의 수명이 연장되고, 나머지 2기의 원자로가 폐쇄되어 추가 폐기물 처분에 대한 요구가 발생하게 되었다. 따라서 6기의 수평터널을 추가로 건설하여 폐기물과 9개의 반응로 용기 처분을 위한 108,000 ㎥의 처분 공간을 확보할 계획으로 스웨덴 방사성폐기물 관리주식회사(SKB)는 SFR3으로의 확장을 위한 허가 신청서를 2014년 정부에 제출하였다. 본 연구에서는 SFR3의 추가 확장계획에 대해 소개하고, SFR3의 계획 시에 고려된 지질학적, 암반공학 및 암반수리학적인 요소들을 소개하였다. The world’s first underground repository for low- and intermediate- level radioactive waste (SFR1) has been in operation since 1988. SFR1 can accommodate 1,000 ㎥ of radioactive waste per year with 4 chambers and 1 silo with a total capacity of 63,000 ㎥ of radioactive waste. With extended operation time of 10 of the 12 nuclear power reactors and dismantling of the other 2 nuclear reactors, more nuclear waste need to be disposed in the future. Therefore, Swedish Nuclear Fuel and Waste Management Company (SKB) submitted a license application for a repository extension (SFR3) that consists of 6 additional rock chambers with a capacity of 108,000 ㎥ of radioactive waste and for accommodating 9 boiling water reactor tanks. In this study, plans for the extension SFR3 are presented with the geological, geomechanical and hydrogeological issues to be considered.

고준위방사성폐기물 심층처분장 모델링을 위한 불연속체 기반 수리-역학 복합거동 해석기법 현황 분석

권새하(Saeha Kwon),김광일(Kwang-Il Kim),이창수(Changsoo Lee),김진섭(Jin-Seop Kim),민기복(Ki-Bok Min) 한국암반공학회 2021 터널과지하공간 Vol.31 No.5

고준위방사성폐기물 심층처분장 내 천연방벽은 방사성핵종의 누출을 방지 및 지연할 수 있는 수리학적 특성을 갖춰야 한다. 결정질 암반의 경우 불연속면에 의해 수리학적 성능이 결정되기 때문에, 불연속면의 수리-역학적 복합거동에 대한 자세한 모사가 필요하다. 불연속체 기반 해석기법은 불연속면의 생성, 전파, 변형, 미끄러짐과 같은 복잡한 거동을 구현할 수 있어 결정질 암반 모사에 적합하다. 본 연구에서는 불연속면에서의 수리-역학 복합거동에 초점을 맞추어, UDEC, 3DEC, PFC, DDA, FRACOD, TOUGH-UDEC과 같은 상용화된 불연속체 기반 수리-역학 복합거동 해석기법을 조사하였다. 블록 기반 불연속체 해석기법의 경우 주로 불연속면 상에서 진행되는 유체 유동을 바탕으로 수리-역학 복합거동을 해석하였고, 그중 일부는 다른 수리학적 해석기법과의 결합을 통하여 모델 전체에 대한 수리-역학적 복 합거동을 제공하였다. 입자 기반 불연속체 해석기법의 경우에는 입자 사이로 흐르는 유체를 반영하여 불 연속체 모델 전체에 해당하는 수리-역학적 복합거동 모사가 가능하다. 현재까지 상용화된 불연속체 기 반 복합거동 해석기법은 2차원 해석만 제공하거나, 수리학적 해석 성능이 떨어지고, 불연속면에서의 유 체 유동만 고려되거나, 자세한 수리학적 해석을 지원하지 않는 등의 한계점이 있어 고준위방사성폐기물 심층처분시스템의 정확한 수리-역학 모델링에는 적합하지 않을 수 있다. 본 기술보고에서 검토한 다양 한 해석기법들의 장단점을 참고하여 향후 처분시스템을 정확하고 자세하게 모사할 수 있는 불연속체 기 반 수리-역학 복합거동 해석기법의 개발이 필요하다. Natural barrier systems surrounding the geological repository for the high-level radioactive waste should guarantee the hydraulic performance for preventing or delaying the leakage of radionuclide. In the case of the behavior of a crystalline rock, the hydraulic performance tends to be decided by the existence of discontinuities, so the coupled hydro-mechanical(HM) processes on the discontinuities should be characterized. The discontinuum modelling can describe the complicated behavior of discontinuities including creation, propagation, deformation and slip, so it is appropriate to model the behavior of a crystalline rock. This paper investigated the coupled HM processes in discontinuum modelling such as UDEC, 3DEC, PFC, DDA, FRACOD and TOUGH-UDEC. Block-based discontinuum methods tend to describe the HM processes based on the fluid flow through the discontinuities, and some methods are combined with another numerical tool specialized in hydraulic analysis. Particle- based discontinuum modelling describes the overall HM processes based on the fluid flow among the particles. The discontinuum methods that are currently available have limitations: exclusive simulations for two-dimension, low hydraulic simulation efficiency, fracture-dominated fluid flow and simplified hydraulic analysis, so it could be improper to the modelling the geological repository. Based on the concepts of various discontinuum modelling compiled in this paper, the advanced numerical tools for describing the accurate coupled HM processes of the deep geological repository should be developed.

DECOVALEX-2019 Task G 소개: EDZ Evolution – 굴착손상영역 평가를 위한 수리전도도 및 투수량계수 측정의 신뢰도, 적합성 및 중요성

권새하(Saeha Kwon),민기복(Ki-Bok Min) 한국암반공학회 2020 터널과지하공간 Vol.30 No.4

사용후핵연료의 심층처분 사업에서는 처분장 주변 모암의 수리역학적 성능을 저하시키는 굴착손상영역의 특성화가 중요하다. 이에 DECOVALEX-2019 프로젝트의 Task G에서는 균열암반 수치해석 모델을 구축한 후 암반 주변의 굴착손상영역의 수리역학적 거동을 모사하고, 구축한 모델로 처분장의 운영 시에 장기적으로 야기될 수 있는 추가적인 수리학적 변화를 관찰하였다. 과업의 첫 번째 단계에서는 2차원 균열암반 모델을 구축하여 수치해석 기법의 특성을 파악하고, 두 번째 단계에서는 3차원 균열암반 모델로 확장 후 스웨덴 애스푀 지하연구시설(Aspo Hard Rock Laboratory) 내 TAS04 간섭시험 결과와 비교하여 수치해석 모델을 검증한 후, 세 번째 단계에서는 열과 빙하 하중에 의한 영향을 반영하여 균열암반의 수리역학적 반응을 순차적으로 확인하였다. 과업의 전 과정에서 유한요소법과 개별요소법으로 균열암반에서의 수리역학적 분석을 수행하였으며, 균열의 기하학적 특성을 반영 및 굴착손상영역을 반영하는 과정에서 각 수치해석 기법에 따라 다양한 접근방법으로 고려하였다. 따라서 본 연구는 향후 결정질 균열암반에 사용후핵연료 처분장을 계획할 시 수치해석 단계에서 채택될 수 있는 다양한 접근 방법과 고려해야 할 사항들을 제시할 수 있을 것으로 전망한다. Characterizations of Excavation Damage Zone (EDZ), which is hydro-mechanical degrading the host rock, are the important issues on the geological repository for the spent nuclear fuel. In the DECOVALEX 2019 project, Task G aimed to model the fractured rock numerically, describe the hydro-mechanical behavior of EDZ, and predict the change of the hydraulic factor during the lifetime of the geological repository. Task G prepared two-dimensional fractured rock model to compare the characteristics of each simulation tools in Work Package 1, validated the extended three-dimensional model using the TAS04 in-situ interference tests from Äspö Hard Rock Laboratory in Work Package 2, and applied the thermal and glacial loads to monitor the long-term hydro-mechanical response on the fractured rock in Work Package 3. Each modelling team adopted both Finite Element Method (FEM) and Discrete Element Method (DEM) to simulate the hydro-mechanical behavior of the fracture rock, and added the various approaches to describe the EDZ and fracture geometry which are appropriate to each simulation method. Therefore, this research can introduce a variety of numerical approaches and considerations to model the geological repository for the spent nuclear fuel in the crystalline fractured rock.

굴착 및 열응력을 고려한 절리암반 내 처분공동 주변에서의 전단영역 및 균열간극 변화 분석

홍수연(Suyeon Hong),권새하(Saeha Kwon),민기복(Ki-Bok Min),지성훈(Sung-Hoon Ji) 한국암반공학회 2021 터널과지하공간 Vol.31 No.2

핀란드의 사용후핵연료 지층처분 현황 및 암반공학 관련 연구소개

홍수연(Suyeon Hong),권새하(Saeha Kwon),민기복(Ki-Bok Min),박의섭(Eui-Seob Park) 한국암반공학회 2019 터널과지하공간 Vol.29 No.4

본 기술보고에서는 세계 최초로 사용후핵연료의 지층처분장 건설에 착수한 핀란드의 방사성폐기물 처분사업과 연구현황을 기술하였다. 핀란드는 1977년 원자력발전을 시작하였고, 현재 4기의 원자력발전소를 운영 중에 있다. 1993년부터 상세 부지조사가 진행되어 2001년에 올킬루오토(Olkiluoto)가 지층처분의 부지로 최종 확정되었으며, 2015년에 건설허가가 발급되었다. 2020년대에 정부에 의해 운영허가가 나면 세계 최초로 지층처분장을 운영하는 사례가 될 것이다. 올킬루오토 부지에 있는 부지특화 지하연구시설인 온칼로(ONKALO)에서는 처분장의 안전성 검증을 위한 다양한 연구들이 수행되었다. 핀란드의 사용후핵연료 처분 부지 암반은 결정암질로 KBS-3 처분개념을 사용하기에, 결정암질 암반이 주를 이루는 한국 또한 유사한 처분개념을 고려 중이다. 핀란드 내의 중저준위 폐기물 처분장 운영 현황과 현재까지 진행된 지층처분장 부지조사 및 선정단계를 포함한 전 과정을 소개하고, 현지 지하연구시설인 온칼로에서의 최신 암반역학 및 수리지질학적 실험 및 수치해석 등의 연구들을 정리하였다. 마지막으로 핀란드의 사례를 바탕으로 한국의 방사성폐기물 처분사업을 위한 방향을 제시한다. This technical note describes the current status of Finnish radioactive waste disposal project which started to construct the repository for spent nuclear waste for the first time in the world. Finland started operating nuclear power plant in 1977 and is currently operating four nuclear power plants. After detailed site surveys started in 1993, Olkiluoto was finally selected by the parliament of Finland as the site for geological disposal in 2001 followed by a construction license in 2015. If the operating license is approved by the government in the 2020s, it would be the world"s first case of geological disposal. In ONKALO, a site-specific underground research facility at the site of Olkiluoto, various studies were conducted to verify the safety of the repository. Finland uses the KBS-3 disposal concept, and Korea considers a similar disposal concept because of similar rock formations. The entire process in Finland including the operation status of intermediate and low-level waste disposal, site investigation and selection stages, and the latest rock mechanics and hydrogeological studies in ONKALO are presented. Suggestions for the radioactive waste disposal in Korea is given based on the Finnish case.