• Title/Summary/Keyword: 처분공

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Review on Discontinuum-based Coupled Hydro-Mechanical Analyses for Modelling a Deep Geological Repository for High-Level Radioactive Waste (고준위방사성폐기물 심층처분장 모델링을 위한 불연속체 기반 수리-역학 복합거동 해석기법 현황 분석)

  • Kwon, Saeha;Kim, Kwang-Il;Lee, Changsoo;Kim, Jin-Seop;Min, Ki-Bok
    • Tunnel and Underground Space
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    • v.31 no.5
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    • pp.309-332
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    • 2021
  • 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.

Gas Injection Experiment to Investigate Gas Migration in Saturated Compacted Bentonite (포화 압축 벤토나이트 내 기체 이동 현상 관측을 위한 기체 주입 시험)

  • Jung-Tae Kim;Changsoo Lee;Minhyeong Lee;Jin-Seop Kim;Sinhang Kang
    • Tunnel and Underground Space
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    • v.34 no.2
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    • pp.89-103
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    • 2024
  • In the disposal environment, gases can be generated at the interface between canister and buffer due to various factors such as anaerobic corrosion, radiolysis, and microbial degradation. If the gas generation rate exceeds the diffusion rate, the gas within the buffer may compress, resulting in physical damage to the buffer due to the increased pore pressure. In particular, the rapid movement of gases, known as gas breakthroughs, through the dilatancy pathway formed during this process may lead to releasing radionuclide. Therefore, understanding these gas generation and movement mechanism is essential for the safety assessment of the disposal systems. In this study, an experimental apparatus for investigating gas migration within buffer was constructed based on a literature review. Subsequently, a gas injection experiment was conducted on a compacted bentonite block made of Bentonile WRK (Clariant Ltd.) powder. The results clearly demonstrated a sharp increase in stress and pressure typically observed at the onset of gas breakthrough within the buffer. Additionally, the range of stresses induced by the swelling phenomenon of the buffer, was 4.7 to 9.1 MPa. The apparent gas entry pressure was determined to be approximately 7.8 MPa. The equipment established in this study is expected to be utilized for various experiments aimed at building a database on the initial properties of buffer and the conditions during gas injection, contributing to understanding the gas migration phenomena.

Development of DHLT Joint for Vertical Cutoff Walls in Offshore Waste Landfill Site (해상처분장 연직차수공을 위한 DHLT 이음부의 개발)

  • Hong, Young-Ho;Lee, Jong-Sub;Lee, Dongsoo;Chae, Kwang-Seok;Yu, Jung-Doung
    • Journal of the Korean Geotechnical Society
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    • v.34 no.3
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    • pp.43-56
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    • 2018
  • Vertical cutoff walls such as steel pipe sheet piles (SPSPs) have been commonly applied for the construction of the offshore waste landfill site. Because the SPSPs are sequentially installed by connecting their joints to those of adjacent piles, their mechanical stability should be ensured against the inherent external forces on the sea. The objective of this study is to evaluate the structural performances of the newly developed types of SPSP joint compared with those of other joint types. The problems of the traditional SPSP joints are investigated, and an advanced joint shape of SPSP, which is named double H with L-T (DHLT) joint, are designed for improving the constructability and maintenance. Full-scale models of the DHLT joint are manufactured, and then its joint areas are filled with grout material. After 28 days of curing time, compressive and tensile strength tests were performed on the joint models and the test results were compared with those of the traditional joints. Experimental results show that the structural capacities of the DHLT joint models are lower than those of traditional joints due to the influence of grout and steel members. In the cases of the compressive strength test, especially, bending occurs on steel H-beam with no distinct cracks in grout due to the asymmetrical structure of joint which has no reaction force. This study shows that the performance of the SPSP joint can be improved by considering the influence factors on the structural capacities estimated by the experimental tests.

A Study on the Temperature Distribution of Rock Mass at KAERI Underground Research Tunnel: Verification on the Result of Borehole Heater Test (지하처분연구시설(KURT) 내 암반의 온도 분포에 관한 연구 : 시추공히터시험 결과의 검증)

  • Yoon, Chan-Hoon;Choi, Young-Chul;Kwon, Sang-Ki;Choi, Heui-Joo
    • Tunnel and Underground Space
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    • v.23 no.4
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    • pp.297-307
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    • 2013
  • In this study, the thermal analysis is carried out for a result of borehole heater test using ABAQUS ver 6.10 based on finite element analysis code. Thermal-mechanical rock properties as determined by laboratory tests before the in situ test and characteristics of the atmosphere at the test section are used as the initial condition. When comparing the results of the in situ test and thermal analysis, the temperature of C3 observation hole that is 0.9 m away from the heater showed very similar patterns and figures (about $1.3^{\circ}C$ difference). But the results of the A and B observation hole showed a significant difference around $15^{\circ}C{\sim}20^{\circ}C$. To find the reason for these results, the over-coring is carried out for the A1 and B1 observation holes. As a result of checking the excavated rock core with the naked eye, there is no problem on the number and position of the sensor as the test plan. However the state of cement injection in the observation hole is poor.

Analysis on Contaminant Transport according to the Embedded Depth of Vertical Barrier of Offshore Landfill (해상 폐기물매립지 연직차수벽체 근입심도에 따른 오염물질 이동특성 분석)

  • Park, Haeyong;Oh, Myounghak;Kwon, Osoon
    • Journal of the Korean GEO-environmental Society
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    • v.17 no.8
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    • pp.29-37
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    • 2016
  • In order to prevent leakage of contaminants in offshore landfill, vertical barrier should be installed. Vertical barrier should be installed at designed depth of seabed to prevent the horizontal transport of contaminant in the subsurface. In this study, the seepage and contaminant transport in the subsurface according to embedded depth of vertical barrier were analyzed by using 2-D finite element analysis program SEEP/W and 3-D finite difference analysis program Visual Modflow. Numerical modelling results show that seepage flux and contaminant transport in seabed was greatly reduced when vertical barrier was installed at certain depth of low permeable layer. Therefore, the determination of minimum embedded depth for preventing contaminant leakage is helpful to design the economical vertical barrier.

Evaluation on Compression Wave Velocities and Moduli of Gyeongju Compacted Bentonite (경주 압축 벤토나이트의 압축파속도와 탄성계수 산정 연구)

  • Balagosa, Jebie;Yoon, Seok;Choo, Yun Wook
    • Journal of the Korean Geotechnical Society
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    • v.35 no.7
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    • pp.41-50
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    • 2019
  • Gyeongju bentonite is a buffer material primarily considered in Korea and it is highly compacted as a part of an engineered barrier system (EBS) of high-level radioactive waste repository. The compacted bentonite undergoes swelling stress by groundwater penetration and thermal stress by decay heat from a canister. Therefore, the mechanical properties of the compacted bentonite buffer material is crucial for the performance assessment of EBS. This paper aims to evaluate deformation properties of Gyeongju compacted bentonite using seismic methods. Two sets of compacted bentonite specimens were prepared having dry densities of $1.59g/cm^3$ and $1.75g/cm^3$ with water contents of 10.6% and 8.7%. Free-free resonant column tests were performed to measure constrained and unconstrained compression wave velocities. With the measured wave velocities, Young's modulus ($E_{max}$) and constrained modulus ($M_{max}$), material damping ratio ($D_{min}$), and Poisson's ratio at small strain were determined. As results, this paper evaluates the deformation properties of Gyeongju compacted bentonite and compares them with the results of previous researches.

Geochemical characteristics of a LILW repository I. Groundwater (중.저준위 방사성 폐기물 처분부지의 지구화학 특성 I. 지하수)

  • Choi, Byoung-Young;Kim, Geon-Young;Koh, Yong-Kwon;Shin, Seon-Ho;Yoo, Si-Won;Kim, Doo-Haeng
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.6 no.4
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    • pp.297-306
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    • 2008
  • This study was carried out to identify the characteristics of hydrochemistry controlling groundwater chemical condition in a repository site of Gyeongju. For this study, 12 bore holes of all monitoring bore holes in the study area were selected and total 46 groundwater samples were collected with depth. In addition, 3 surfacewater samples and 1 seawater sample were collected. For water samples, cations and anions were analyzed. The environmental isotopes(${\delta}^{18}O-{\delta}D$, Tritium, ${\delta}^{13}C,\;{\cdot}{\delta}^{34}S$) were also analyzed to trace the origin of water and solutes. The result of ${\delta}^{18}O\;and\;{\delta}D$ analysis showed that surface water and groundwater were originated from precipitation. Tritium concentrations of groundwater decreased with depth but high concentrations of tritium indicated that groundwater was recharged recently. The results of ion and correlation analysis showed that groundwater types of the study area were represented by Ca-Na-$HCO_3$ and Na-Cl-$SO_4$, which was caused by sea spray and water-rock interaction. Especially, high ratio of Na content in groundwater resulted from ion exchange. For redox condition of groundwater, the values of DO and Eh decreased with depth, which indicated that reducing condition was formed in deeper groundwater. In addtion, high concentration of Fe and Mn showed that redox condition of groundwater was controlled by the reduction of Fe and Mn oxides.

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Study on Moye's Method for Analysis of Constant-Head Tests Conducted in Crystalline Rock (결정질 암반에서 Moye 방법을 이용한 정압시험의 해석에 대한 고찰)

  • Kyung-Woo Park;Byeong-Hak Park;Sung-Hoon Ji;Kang-Kun Lee
    • The Journal of Engineering Geology
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    • v.33 no.4
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    • pp.519-530
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    • 2023
  • Moye's analytical solution was examined as a method for constant-head tests under steady-state conditions, and results were compared with transient-state analyses in in situ hydraulic tests. The sensitivity of hydraulic conductivities calculated using Moye's method increased with the length of the test section, which should be as large as possible under test conditions. Particularly in low-permeability media with less than 10-8 m/sec of hydraulic conductivity, hydraulic conductivity is lower than that under transient-state conditions and can be recalculated by adjusting the boundary between radial and spherical flow assumed in Moye's equation. Constant-head tests performed in the research borehole at the KAERI Underground Research Tunnel (KURT) indicated that transmissivities derived from the constant-head withdrawal test under transient-state conditions in low-permeability media were higher than those derived from steady-state tests, likely because the groundwater flow boundary was smaller than the "half of the test-section length"assumed by Moye's equation. When interpreting constant-head test results for crystalline rock, the hydrogeological properties of the medium may be better understood by considering assumed conditions accompanying analysis of the steady-state condition and comparing them with results for the transient-state analysis, rather than simply assuming properties based on steady-state analyses.

Review of Erosion and Piping in Compacted Bentonite Buffers Considering Buffer-Rock Interactions and Deduction of Influencing Factors (완충재-근계암반 상호작용을 고려한 압축 벤토나이트 완충재 침식 및 파이핑 연구 현황 및 주요 영향인자 도출)

  • Hong, Chang-Ho;Kim, Ji-Won;Kim, Jin-Seop;Lee, Changsoo
    • Tunnel and Underground Space
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    • v.32 no.1
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    • pp.30-58
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    • 2022
  • The deep geological repository for high-level radioactive waste disposal is a multi barrier system comprised of engineered barriers and a natural barrier. The long-term integrity of the deep geological repository is affected by the coupled interactions between the individual barrier components. Erosion and piping phenomena in the compacted bentonite buffer due to buffer-rock interactions results in the removal of bentonite particles via groundwater flow and can negatively impact the integrity and performance of the buffer. Rapid groundwater inflow at the early stages of disposal can lead to piping in the bentonite buffer due to the buildup of pore water pressure. The physiochemical processes between the bentonite buffer and groundwater lead to bentonite swelling and gelation, resulting in bentonite erosion from the buffer surface. Hence, the evaluation of erosion and piping occurrence and its effects on the integrity of the bentonite buffer is crucial in determining the long-term integrity of the deep geological repository. Previous studies on bentonite erosion and piping failed to consider the complex coupled thermo-hydro-mechanical-chemical behavior of bentonite-groundwater interactions and lacked a comprehensive model that can consider the complex phenomena observed from the experimental tests. In this technical note, previous studies on the mechanisms, lab-scale experiments and numerical modeling of bentonite buffer erosion and piping are introduced, and the future expected challenges in the investigation of bentonite buffer erosion and piping are summarized.

A Stress Analysis of the Cast Iron Insert of Spent Nuclear Fuel Disposal Canister with the Underground Water Pressure Variation in a Deep Repository (지하수압 변화에 따른 심지층 핵폐기물 처분용기 내부 주철 구조물의 응력해석)

  • 강신욱;권영주
    • Proceedings of the Computational Structural Engineering Institute Conference
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    • 2000.04b
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    • pp.77-84
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    • 2000
  • In this paper, the stress analysis of the cast iron insert of spent nuclear fuel disposal canister in a deep repository at 500m underground is done for the underground pressure variation. Since the nuclear fuel disposal usually emits much heat and radiation, its careful treatment is required. And so a long term safe repository at a deep bedrock is used. Under this situation, the canister experiences some mechanical external loads such as hydrostatic pressue of underground water, swelling pressure of bentonite, sudden rock movement etc.. Hence, the canister should be designed to withstand these loads. The cast iron insert of the canister mainly supports these loads. Therefore, the stress analysis of the cast iron insert is done to determine the design variables such as the diameter versus length of canister and the number and array type of inner baskets in this paper, The linear static structural analysis is done using the finite element analysis method. And the finite element analysis code, NISA, is used for the computation.

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