• 제목/요약/키워드: Rock Waste

검색결과 360건 처리시간 0.025초

Rock wool wastes as a supplementary cementitious material replacement in cement-based composites

  • Lin, Wei-Ting;Cheng, An;Huang, Ran;Wu, Yuan-Chieh;Han, Ta-Yuan
    • Computers and Concrete
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    • 제11권2호
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    • pp.93-104
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    • 2013
  • The use of rock wool waste, an industrial by-product, in cement-based composites has positive effects on the environment because it reduces the problems associated rock wool disposal. The experiments in this study tested cement-based composites using various rock wool waste contents (10, 20, 30 and 40% by weight of cement) as a partial replacement for Portland cement in mortars. The pozzolanic strength activity test, flow test, compressive strength test, dry shrinkage test, absorption test, initial surface absorption test and scanning electron microscope observations were conducted to evaluate the properties of cement-based composites. Test results demonstrate that the pozzolanic strength activity index for rock wool waste specimens is 103% after 91 days. The inclusion of rock wool waste in cement-based composites decreases its dry shrinkage and initial surface absorption, and increases its compressive strength. These improved properties are the result of the dense structure achieved by the filling effect and pozzolanic reactions of the rock wool waste. The addition of 30% and 10% rock wool wastes to cement is the optimal amount based on the results of compressive strength and initial surface absorption for a w/cm of 0.35 and 0.55, respectively. Therefore, it is feasible to utilize rock wool waste as a partial replacement of cement in cement-based composites.

미국 Waste Isolation Pilot Plant에서의 시간변동 거동 계측 (In-situ Measurements of Time-dependent Rock Deformations at the Waste Isolation Pilot Plant in USA)

  • Sangki Kwon;Chul-Hyung Kang;Jongwon Choi
    • 터널과지하공간
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    • 제9권3호
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    • pp.175-184
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    • 1999
  • 현장에서의 체계적인 측정자료는 최적의 안전한 설계를 위한 중요한 정보라 할 수 있다. 본 연구에서는 미국의 방사성폐기물 저장 시설인 Waste Isolation Pilot Plant(WIPP)에서 수행된 현장 측정 기법들에 대해 고찰하였다. 또한 지하구조물의 시간 의존적인 복잡한 거동을 이해하기 위해서 필요한 측정기기의 설치와 측정에 대하여 논의하였다.

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Effect of Rock Mass Properties on Coupled Thermo-Hydro-Mechanical Responses at Near-Field Rock Mass in a Heater Test - A Benchmark Sensitivity Study of the Kamaishi Mine Experiment in Japan

  • Hwajung Yoo;Jeonghwan Yoon;Ki-Bok Min
    • 방사성폐기물학회지
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    • 제21권1호
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    • pp.23-41
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    • 2023
  • 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 TOUGH-FLAC 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.

방사성 폐기물의 열하중에 의한 절리암반의 거동에 관한 수치해석적 연구 (A Numerical Study on the Response of Jointed Rock Mass Due to Thermal Loading of Radioactive Waste)

  • 문현구;주광수
    • 터널과지하공간
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    • 제4권2호
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    • pp.102-118
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    • 1994
  • Thermomechanical analysis is conducted on the radioactive repository in deep rock mass considering the in-situ stress, excavation and thermal loading of a radioactive waste. Thermomechanical properties of a discontinuous rock mass are estimated by a theoretical method so called sequential analysis. Using the estimated properties as input for finite element analysis, the influence on temperature distribution and thermal stress is analyzed within the scope of 2-dimensional steady state and transient heat transfer and coupled thermal elastic plastic behaviour. Granitic rock mass is taken for this analysis. The analysis is done for two different rock mass conditions, i.e. continuous-homogeneous and highly jointed conditions, for the purpose of comparison. In the case of steady state, the extent of disturbed zone around the storage tunnel due to the heat production of the spent-fuel canister varies depending on the thermomechanical properties of the rock mass. In the case of transient analyses, the response of the jointed rock mass to the thermal loading after radioactive waste disposal varies significantly with time, resulting in dramatic changes in the both size and location of disturbed zone.

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임기광산 폐석적치장의 수리침투특성 분석

  • 지상우;정영욱;임길재
    • 한국지하수토양환경학회:학술대회논문집
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    • 한국지하수토양환경학회 2004년도 임시총회 및 추계학술발표회
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    • pp.394-398
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    • 2004
  • This study was carried out to plan the prevention of the generation and discharge of acid mine drainage (AMD). Hydraulic characteristics were tested with the disk tension infiltrometer around the waste rock dump of the Imgi abandoned pyrophyllite mine in Busan, Korea. Because the waste rock dump of the Imgi mine have very low infiltration rate, most of rain was expected flowing into adjoined stream through the slope or plane as surface flow rather then throughflow or ground water. But slopes of the waste rock dump have many 'V' type erosion gullies and consist multi-layers. These gullies and multi-layers have coarse clastic particle layer which have very large hydraulic conductivity. So through these coarse clastic particle layers a large part of rain flow into ground. And also these layers could be played a function of aeration path, which induced oxidation of sulfide minerals and generation of AMD continuously.tinuously.

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폐석적치장의 산성배수발생 및 수리특성 분석 (The Acid Rock Drainage and Hydraulic Characteristics of the Waste Rock Dump)

  • 정영욱;지상우;임길재
    • 한국지반환경공학회 논문집
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    • 제5권4호
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    • pp.13-24
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    • 2004
  • 부산광역시 소재 폐납석광산인 임기광산 채굴적 및 폐석적치장 및 하상퇴적물에 대해 산-염기 평가(ABA test)와 폐석적치장 상부에 대해 디스크-장력침투계를 이용하여 수리특성을 분석하였다. 임기광산 폐석적치장 주변에서 최대 산 발생력(MPA)은 246.942kg $H_2SO_4/t$였고, 산 중화능력(ANC)은 최대 8.7kg $H_2SO_4/t$로 나타나 노출된 채굴적 암반 및 폐석은 ARD를 발생하는 지질물질로 나타났다. 또한 이들에는 이미 황화광물이 산화되어 암석 표면에 염 및 자유수소 이온을 보유하여 강우와 접촉시 표층수 및 침투수 등을 ARD로 변화시키는 지구화학적 특성을 지닌 상태로 판단된다. 임기광산의 폐석적치장은 비록 매우 낮은 침투율을 갖고 있으나 폐석적치장 법면부에 심한 침식작용으로 V자형 침식골이 노출되어 있고 노출부위에 수리전도도가 큰 쇄설층들이 노출되어 강우의 침투경로 역할을 할 것으로 판단된다. 이러한 굵은 쇄설성 입자층의 노출은 지표에서 생성된 ARD 통로 기능뿐만 아니라 공기의 이동 경로가 되어 폐석내 포함된 황화광물의 지속적인 산화작용을 유발시키는 수리적 특성을 보유한다고 할 수 있다.

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방사성폐기물 동굴처분과 지하시험시설 (Rock Cavern for Radioactive Waste Disposal and Underground Research)

  • 강병무
    • 화약ㆍ발파
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    • 제9권2호
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    • pp.19-30
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    • 1991
  • The trend of Radio active waste disposal project is generally to choose The Rock Cavern type because it is the most safest and easy to get concent from The neighbor hood. On the Construction of rock Cavern for R -A. W.0 has to take care follows ; The first of all, to survey rock crack formation. 2nd, The Movement of Underground water. 3rd, Nuclear and Geochemical problems. 4th, to examine physical feature of rocks ets.

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KURT 내 열전달계수 결정에 관한 실험적 연구 (Experimental Study on the Determination of Heat Transfer Coefficient for the KURT)

  • 윤찬훈;권상기;김진
    • 터널과지하공간
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    • 제19권6호
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    • pp.507-516
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    • 2009
  • 고준위 방사성 폐기물 처분장의 경우 폐기물의 방사성 붕괴에 의해 발열 현상이 나타나게 되며, 암반을 통한 열전달에 의해 처분장 주변 환경이 변화됨으로써 처분장의 안전성에 영향을 미칠 수 있다. 그러므로 처분장의 안전성 확보를 위해선 적절한 처분장 내 환기장치가 필요하다. 적절한 환기시스템의 구축을 위해서는 암반 열물성치와 처분장 내 열전달계수의 산정을 통한 컴퓨터 시뮬레이션 연구가 핵심이라고 할 수 있다. 이에 본 연구에서는 KAERI Underground Research Tunnel(이하 KURT) 내부 환경 인자(건습구온도, 암반표면온도, 대기압)들의 측정을 통해 열전달계수를 산정하는 것에 초점을 맞추었다. KURT 내부 우측 연구모듈의 막장 벽면에 길이 2 m, 용량 5 kw의 히터가 $90^{\circ}C$로 암반 내부를 가열하고 있는 히터구간의 열전달계수 산정 결과, 태양의 위치에 따른 처분장 외부 대기의 온도변화에 의해 열전달계수의 수치 변화가 최대 7.9% 발생하였으며, 평균 열전달계수 h는 약 4.533 W/$m^2{\cdot}K$의 수치를 나타내었다.

고준위 방사성폐기물 처분장에서의 THM 상호반응의 수학적 모델 개발 (Mathematical Modelling on THM Coupling in High-Level Radioactive Waste Repository)

  • 황용수;김진웅;강철형
    • 터널과지하공간
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    • 제8권1호
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    • pp.26-36
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    • 1998
  • To assess the groundwater flow near high-level radioactive waste repositories, it is important to understand the effect of coupling among thermal, hydraulic, and mechanical effects. In this paper, detailed mathematical approach to model the groundwater flow near the waste form surrounded by buffer, influenced by decay heat of radioactive waste along with stress change is developed. Two cases(1) before the full expansion of buffer and (2) after the full expansion of buffer are modelled. Based on the mathematical models in this paper, detailed numerical study shall be pursued later.

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