• Title/Summary/Keyword: Rock Waste

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A Study on the Preparation ana Mechanical Properties of Composites Reinforced FRP Waste and Rock-Crush Sludge (폐 FRP/석분슬러지 충전 복합재의 제조 및 기계적 물성에 관한 연구)

  • 황택성;박진원;이철호
    • Polymer(Korea)
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    • v.24 no.6
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    • pp.829-836
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    • 2000
  • In order to recyle the FRP waste from SMC bathtubs and rock-crush sludge obtained as a byproduct of stones, the composite consisting of the FRP and rock-crush sludge and the unsaturated polyester matrix resin were prepared. To enhance the interfacial bonding force between the reinforcements and the matrix resin, the rock-crush sludge was treated with silane coupling agent, ${\gamma}$-methacryloxypropyltrimethoxysilane (${\gamma}$-MPS) and their mechanical properties and interface phenomena were examined. The flexural modulus of the composite containing 10 wt% rock-crush powder treated with 3 wt% silane coupling agent showed the maximum value. And also the initial thermal degradation temperature of composites were in the range of 352~359$^{\circ}C$. From these results, we observed that the weight loss of composites was almost constant regardless of the concentration of silane coupling agent. It is confirmed that the interface of the composites containing filler treated with ${\gamma}$-MPS was improved in that there were no pull-out phenomena between the reinforcement and matrix resin.

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Analysis of Benchmark Test Model for Evaluation of Damage Characteristics of Rock Mass near Radioactive Waste Repository (방사성폐기물 처분장 주변 암반의 손상 특성 고찰을 위한 벤치마크 시험 모델 해석)

  • Lee, Hee-Suk
    • Tunnel and Underground Space
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    • v.17 no.1 s.66
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    • pp.32-42
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    • 2007
  • Severe damage can occur around deposition holes due to complex interaction of thermo-hydro-mechanical (THM) loading during the long term operation of high level radioactive waste repository. Many candidate sites for repository are located in crystalline rock mass, therefore mechanism of damage follows the form of brittle fracture and failure. This paper briefly introduces major outcomes from 15 years international collaborative project, DECOVALEX, and presents major study results for current ongoing benchmark test study from DECOVALEX-THMC, to evaluate the effect of THM loading to rock mass in excavation damaged zone (EDZ) near deposition holes. Through benchmark test model by simplifying THM loading to boundary loading obtained numerical results are compared, and discrete fracture interaction after up to 1 million years operation is discussed.

Case Studies on the Experiments for Long-Term Shear Behavior of Rock Discontinuities (암반 내 불연속면의 장기 전단 거동 평가를 위한 고찰)

  • Juhyi Yim;Saeha Kwon;Seungbeom Choi;Taehyun Kim;Ki-Bok Min
    • Tunnel and Underground Space
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    • v.33 no.1
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    • pp.10-28
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    • 2023
  • Long-term shear behavior of the rock discontinuities should be analyzed and its stability should be evaluated to ensure the long-term stability of a high-level radioactive waste disposal repository. The long-term shear behavior of the discontinuities can be modeled with creep and RSF models. The shear creep test, velocity step test, and slide-hold-slide test can be performed to determine their model parameters or analyze the shear behavior by experiments under various conditions. Testing apparatuses for direct shear, triaxial compression, and biaxial shear were mainly used and improved to reproduce the thermo-hydro-mechanical conditions of local bedrock, and it was confirmed that the shear behavior could vary. In order to design a high-level radioactive waste disposal site in Korea, the long-term behavior of rock discontinuities should be investigated in consideration of rock types, thermo-hydro-mechanical conditions, metamorphism, and restoration of shear resistance.

THE PERFORMANCE OF CLAY BARRIERS IN REPOSITORIES FOR HIGH-LEVEL RADIOACTIVE WASTE

  • Pusch, Roland
    • Nuclear Engineering and Technology
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    • v.38 no.6
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    • pp.483-488
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    • 2006
  • Highly radioactive waste is placed in metal canisters embedded in dense clay termed buffer. The radioactive decay is associated with heat production, which causes degradation of the buffer and thereby time-dependent loss of its waste-isolating potential. The buffer is prepared by compacting air-dry smectite clay powder and is initially not fully water saturated. The evolution of the buffer starts with slow wetting by uptake of water from the surrounding rock followed by a long period of exposure to heat, pressure from the rock and chemical reactants. It can be described by conceptual and theoretical models describing processes related to temperature (T), hydraulic (H), mechanical (M) and chemical performance (C). For temperatures below 90 C more than 75 % of the smectite will be preserved for 100 000 years but cementation may reduce the excellent performance of the buffer to a yet not known extention.

A Study on Characteristics of Jointed Rock Masses and Thermo-hydro-mechanical Behavior of Rock Mass under High Temperature (방사성 폐기물 저장을 위한 불연속 암반의 특성 및 고온하에서의 암반의 수리열역학적 상호작용에 관한 연구)

  • 이희근;김영근;이희석
    • Tunnel and Underground Space
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    • v.8 no.3
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    • pp.184-193
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    • 1998
  • In order to dispose radioactive wastes safely, it is needed to understand the mechanical, thermal, fluid behavior of rockmass and physico-chemical interactions between rockmass and water. Also, the knowledge about mechanical and hydraulic properties of rocks is required to predict and to model many conditions of geological structure, underground in-situ stress, folding, hot water interaction, intrusion of magma, plate tectonics etc. This study is based on researches about rock mechanics issues associated with a waste disposal in deep rockmass. This paper includes the mechanical and hydraulic behavior of rocks in varying temperature conditions, thermo-hydro-mechanical coupling analysis in rock mass and deformation behavior of discontinuous rocks. The mechanical properties were measured with Interaken rock mechanics testing systems and hydraulic properties were measured with transient pulse permeability measuring systems. In all results, rock properties were sensitive to temperature variation.

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