• Title/Summary/Keyword: Rock Waste

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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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    • v.11 no.2
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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.

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

  • Sangki Kwon;Chul-Hyung Kang;Jongwon Choi
    • Tunnel and Underground Space
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    • v.9 no.3
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    • pp.175-184
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    • 1999
  • Systematic measurements in the field are the key component in the design process to ensure that optimal and safe designs result. The instruments installed at the Waste Isolation Pilot Plant, a underground nuclear waste repository in U.S., for measuring rock deformation was reviewed. Also discussions about installation and measurement for better understanding the complex time-dependent deformational behavior of underground excavation were made.

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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
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.21 no.1
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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.

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

  • 문현구;주광수
    • Tunnel and Underground Space
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    • v.4 no.2
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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
    • Proceedings of the Korean Society of Soil and Groundwater Environment Conference
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    • 2004.09a
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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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The Acid Rock Drainage and Hydraulic Characteristics of the Waste Rock Dump (폐석적치장의 산성배수발생 및 수리특성 분석)

  • Cheong, Young Wook;Ji, Sang Woo;Yim, Gil Jae
    • Journal of the Korean GEO-environmental Society
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    • v.5 no.4
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    • pp.13-24
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    • 2004
  • This study was carried out to plan the prevention of the generation and discharge of Acid Rock Drainage (ARD). The Acid Base Accounting(ABA) test was performed for geological materials such as pit wall, waste rock and stream sediments near the Imgi abandoned pyrophyllite mine in Busan, Korea. In addition, hydraulic characteristics were tested with the disk tension infiltrometer around the waste rock dump. Maximum Potential Acidity(MPA) of geological materials near the Imgi mine was 246.942kg $H_2SO_4/t$, and maximum Acid Neutralising Capacity(ANC) was 8.7kg $H_2SO_4/t$. These results indicate the pit wall and waste rock, except most of stream sediments are acid generating geological materials. These have salt and free hydrogen ion which resulted from oxidation of sulfides. Hence they could be convert rain water to acid rock drainage. Although the waste rock dump of the Imgi mine have very low infiltration rate, slopes of the waste rock dump have many "V" type erosion gullies and multi-layers. These gullies and multi-layers have coarse clastic particle layers which have very large hydraulic conductivity. Through this coarse clastic particle layer a large part of rain flow into ground. And also this layer could function as aeration path which induced oxidation of sulfide minerals and generation of ARD continuously.

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

  • Kang Byong Mu
    • Explosives and Blasting
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    • v.9 no.2
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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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Experimental Study on the Determination of Heat Transfer Coefficient for the KURT (KURT 내 열전달계수 결정에 관한 실험적 연구)

  • Yoon, Chan-Hoon;Kwon, Sang-Ki;Kim, Jin
    • Tunnel and Underground Space
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    • v.19 no.6
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    • pp.507-516
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    • 2009
  • In cases of high-level radioactive waste repositories, heat load is apparent by radioactive waste decay. The safety of a waste repository would be influenced by changing circumstances caused by heat transfer through rock. Thus, a ventilation system is necessary to secure the waste repository. The first priority for building an appropriate ventilation system is completing a computer simulation research with thermal rock properties and a heat transfer coefficient. In this study, the heat transfer coefficient in KURT was calculated using the measurement of inner circumstance factors that include dry bulb and wet bulb temperature, rock surface temperature, and barometric pressure. The heater that is 2 m in length and 5 kw in capacity heats the inside of rock in the research module by $90^{\circ}C$. As a result of determining the heat transfer coefficient in the heating section, the changes of heat transfer coefficient were found to be a maximum of 7.9%. The average heat transfer coefficient is approximately 4.533 w/$m^2{\cdot}K$.

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

  • 황용수;김진웅;강철형
    • Tunnel and Underground Space
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    • v.8 no.1
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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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