• Title, Summary, Keyword: high level radwaste

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Carrying Out and Management of High Level Solid Radwaste for Hot Cell in IMEF (조사재시험시설의 핫셀 내부 고준위 고체폐기물 반출 및 처리)

  • 주용선;송웅섭;김도식;유병옥;정양홍;백승제;오완호;이은표;홍권표
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • pp.168-171
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    • 2003
  • The IMEF(Irradiated Materials Examination Facility), located in KAERI site, is a hot cell facility to test and evaluate the irradiation defects or embrittlement through post-irradiation examination(PIEs) of irradiated nuclear fuels and structural materials which are come from HANARO research reactor and commercial nuclear power plants. Therefore, to carry out its own function, the high level solid radioactive wastes, produced through PIEs, are periodically carried out and managed from hot cell to monolith. So far, approximately 30 drums which contains 50 liters are transported to monolith, and it is shown that the quantity is slowly increasing, In this paper, the procedures and work contents of the high level solid radwaste carrying out and management for IMEF are described in detail.

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Analysis of a Groundwater Flow System in Fractured Rock Mass Using the Concept of Hydraulic Compartment (수리영역 개념을 적용한 단열암반의 지하수유동체계 해석)

  • Cho Sung-Il;Kim Chun-Soo;Bae Dae-Seok;Kim Kyung-Su;Song Moo-Young
    • The Journal of Engineering Geology
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    • v.16 no.1
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    • pp.69-83
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    • 2006
  • This study aims to evaluate a complex groundwater flow system around the underground oil storage caverns using the concept of hydraulic compartment. For the hydrogeological analysis, the hydraulic testing data, the evolution of groundwater levels in 28 surface monitoring boreholes and pressure variation of 95 horizontal and 63 vertical water curtain holes in the caverns were utilized. At the cavern level, the Hydraulic Conductor Domains(fracture zones) are characterized one local major fracture zone(NE-1)and two local fracture zones between the FZ-1 and FZ-2 fracture zones. The Hydraulic Rock Domain(rock mass) is divided into four compartments by the above local fracture zones. Two Hydraulic Rock Domains(A, B) around the FZ-2 zone have a relatively high initial groundwater pressures up to $15kg/cm^2$ and the differences between the upper and lower groundwater levels, measured from the monitoring holes equipped with double completion, are in the range of 10 and 40 m throughout the construction stage, indicating relatively good hydraulic connection between the near surface and bedrock groundwater systems. On the other hand, two Hydraulic Rock Domains(C, D) adjacent to the FZ-1, the groundwater levels in the upper and lower zones are shown a great difference in the maximum of 120 m and the high water levels in the upper groundwater system were not varied during the construction stage. This might be resulted from the very low hydraulic conductivity$(7.2X10^{-10}m/sec)$ in the zone, six times lower than that of Domain C, D. Groundwater recharge rates obtained from the numerical modeling are 2% of the annual mean precipitation(1,356mm/year) for 20 years.

Mechanical Stability Analysis of a High-Level Waste Repository for Determining Optimum Cavern and Deposition Hole Spacing (고준위폐기물 처분장의 최적 공동간격 및 처분공간격을 결정하기 위한 역학적 안정성 해석)

  • 박병윤;권상기
    • Tunnel and Underground Space
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    • v.10 no.2
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    • pp.237-248
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    • 2000
  • Based on the preliminary results from the therm analysis, which is currently carrying, three-dimensional computer simulations using a finite element code, ABAQUS Ver. 5.8, were designed to determine the mechanically stable cavern and deposition hole spacing. Linear elastic modeling for the cases with different cavern and deposition hole spacing were carried out under three different in situ stress conditions. From the simulations, the response of the rock to the stress redistribution after the excavation of the openings could be investigated. Also the optimum cavern and deposition hole spacing could be estimated based on the factor of safety. When the in situ stress determined from the actual stress measurements in Korea were used, the case with cavern spacing of 40m and deposition hole spacing of 3m was in very stable condition, because the factor of safety was calculated as 3.42., When the in situ stress conditions for Sweden and Canada were used, the previous case, they seem to be in stable condition, since the factors of safety are still higher than 1.0. From these results, it was concluded that the rock will not fail even after the stress redistribution.

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A Study on the Manufacturing Characteristics and Field Applicability of Engineering-scale Bentonite Buffer Block in a High-level Nuclear Waste Repository (고준위폐기물처분장 내 공학규모의 균질 완충재 블록 성형특성 및 현장적용성 분석)

  • Kim, Jin-Seop;Yoon, Seok;Cho, Won-Jin;Choi, Young-Chul;Kim, Geon-Young
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.16 no.1
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    • pp.123-136
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    • 2018
  • The objective of this study is to propose a new methodology to fabricate a reliable engineering-scale buffer block, which shows homogeneous and uniform distribution in buffer block density, for in-situ experiments. In this study, for the first time in Korea, floating die press and CIP (Cold Isostatic Press) are applied for the manufacture of an engineering-scale bentonite buffer. The optimized condition and field applicability are also evaluated with respect to the method of manufacturing the buffer blocks. It is found that the standard deviation of the densities obtained decreases noticeably and that the average dry density increases slightly. In addition, buffer size is reduced by about 5% at the same time. Through the test production, it is indicated that the stress release phenomenon decreases after the application of the CIP method, which leads to a reduction in crack generation on the surface of the buffer blocks over time. Therefore, it is confirmed that the production of homogeneous buffer blocks on industrial scale is possible using the method suggested in this study, and that the produced blocks also meet the design conditions for dry density of buffer blocks in the AKRS (Advanced Korea Reference Disposal System of HLW).

Thermohydromechanical Behavior Study on the Joints in the Vicinity of an Underground Disposal Cavern (심부 처분공동 주변 절리에서의 열수리역학적 거동변화)

  • Jhin wung Kim;Dae-seok Bae
    • The Journal of Engineering Geology
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    • v.13 no.2
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    • pp.171-191
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    • 2003
  • The objective of this present study is to understand long term(500 years) thermohydromechanical interaction behavior on joints adjacent to a repository cavern, when high level radioactive wastes are disposed of within discontinuous granitic rock masses, and then, to contribute this understanding to the development of a disposal concept. The model includes a saturated discontinuous granitic rock mass, PWR spent nuclear fuels in a disposal canister surrounded with compacted bentonite inside a deposition hole, and mixed bentonite backfilled in the rest of the space within a repository cavern. It is assumed that two joint sets exist within a model. Joint set 1 includes joints of $56^{\circ}$ dip angle, spaced 20m apart, and joint set 2 is in the perpendicular direction to joint set 1 and includes joints of $34^{\circ}$ dip angle, spaced 20m apart. The two dimensional distinct element code, UDEC is used for the analysis. To understand the joint behavior adjacent to the repository cavern, Barton-Bandis joint model is used. Effect of the decay heat from PWR spent fuels on the repository model has been analyzed, and a steady state flow algorithm is used for the hydraulic analysis.