• Title/Summary/Keyword: High level waste

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고준위방사성폐기물 처분장 내 열-수리-역학-화학적 복합거동 해석을 위한 국제공동연구 DECOVALEX-2023에서 수행 중인 연구 과제 소개 (Introduction to Tasks in the International Cooperation Project, DECOVALEX-2023 for the Simulation of Coupled Thermohydro-mechanical-chemical Behavior in a Deep Geological Disposal of High-level Radioactive Waste)

  • 김태현;이창수;김정우;강신항;권새하;김광일;박정욱;박찬희;김진섭
    • 터널과지하공간
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    • 제31권3호
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    • pp.167-183
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    • 2021
  • 고준위방사성폐기물 처분장의 장기 안전성 확보를 위해서는 공학적방벽 및 천연방벽 내에서 발생하는 복잡한 열-수리-역학-화학적(THMC) 복합거동 해석에 대한 이해가 필수적이다. 특히 고준위방사성폐기물에서 발생하는 열로 인해 암반 및 완충재 내의 지하수에서 압력 증가 및 상변화가 발생하게 되며, 지하수의 유입으로 인해 공학적방벽 내 포화도가 변화하게 된다. 또한 포화도의 변화는 완충재 내에서의 열전달 및 다상 유동 특성에 영향을 미치게 된다. 따라서 복합거동 특성의 복잡성으로 인해 수치해석은 처분시스템에서의 THMC 복합거동 평가와 예측 및 안전성 평가에 있어 강점을 지니고 있으며, DECOVALEX 국제공동연구는 THMC 복합거동에 대한 이해도 증진 및 해석기법 검증을 목적으로 1992년부터 시작되었다. 국내에서는 2008년부터 한국원자력연구원이 지속적으로 참여하여 연구를 수행하고 있으며, 본 기술보고에서는 현재 진행 중인 DECOVALEX-2023의 주요 연구내용을 국내 암반 및 지반공학자들에게 소개하였다.

동굴 안정성 입력자료로서의 탄성계수(Es)결정

  • 김정대;박인식
    • 터널과지하공간
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    • 제1권
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    • pp.32-38
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    • 1991
  • 9 nuclear power plants are presently in operation in Korea. They produce radioactive waste of which the most long-lived radioactive elements need to be safely stored for hundreds of thousands of years, isolated from humanity and the environment. The safe disposal of high level radioactive waste in mined cavities requires knowledge of the mechanical. thermal and fluid flow characteristics of rock as perturbed by a thermal pulse The literature review was performed to assemble data on the following properties: modulus tensile strength compressive strength thermal expansion specific heat, thermal conductivity thermal diffusivity and permeability.

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Waste glass powder and its effect on the fresh and mechanical properties of concrete: A state of the art review

  • He, Zhi-hai;Yang, Ying;Zeng, Hao;Chang, Jing-yu;Shi, Jin-yan;Liu, Bao-ju
    • Advances in concrete construction
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    • 제10권5호
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    • pp.417-429
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    • 2020
  • Waste glass is a global solid waste with huge reserves. The discarded waste glass has caused a series of problems such as resource waste and environmental pollution, so it is urgent to recycle waste glass with high replacement level. Glass powder (GP), as a supplementary cementitious material (SCM), used in cement-based materials has already become one of the important ways to recycle waste glass mainly attributed to its pozzolanic reaction and filling effect, especially to the suppressed ASR expansion. This paper demonstrates an overview of the properties of GP and its effect on the fresh and mechanical properties of cement-based materials. The study found that the influence of GP on the performance of cement-based materials mainly depends on its content, particle size, color and type, curing conditions, and other SCMs. Finally, based on the problems involved in the investigation of concrete containing GP, some corresponding suggestions and efforts are given to further guide the utilization of GP in cement-based materials.

방사선폐기물 원격감시용 이동로봇 (A Mobile Robot for Remote Inspection of Radioactive Waste)

  • 서용칠;김창회;조재완;최영수;김승호
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2004년도 학술논문집
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    • pp.430-432
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    • 2004
  • Tele-operation and remote monitoring techniques are essential and important technologies for the inspection and maintenance of the radioactive waste. A mobile robot has been developed for the application of remote monitoring and inspection of nuclear facilities, where human access is limited because of the high-level radioactive environments, The mobile robot was designed with reconfigurable crawler type of wheels attached on the front and rear side in order to pass through the ditch, The extendable mast, mounted on the mobile robot, car be extended up to 8 m vertically. The robust controller for radiation is designed in focus on electric components to prevent abnormal operation in a highly radioactivated area during reactor operation, This robot system will enhance the reliability of nuclear power facilities, and cope with the unexpected radiation accident.

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

  • Pusch, Roland
    • Nuclear Engineering and Technology
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    • 제38권6호
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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.

DEVELOPMENT OF ELECTROREFINER WASTE SALT DISPOSAL PROCESS FOR THE EBR- II SPENT FUEL TREATMENT PROJECT

  • Simpson, Michael F.;Sachdev, Prateek
    • Nuclear Engineering and Technology
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    • 제40권3호
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    • pp.175-182
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    • 2008
  • The results of process development for the blending of waste salt from the electrorefining of spent fuel with zeolite-A are presented. This blending is a key step in the ceramic waste process being used for treatment of EBR-II spent fuel and is accomplished using a high-temperature v-blender. A labscale system was used with non-radioactive surrogate salts to determine optimal particle size distributions and time at temperature. An engineering-scale system was then installed in the Hot Fuel Examination Facility hot cell and used to demonstrate blending of actual electrorefiner salt with zeolite. In those tests, it was shown that the results are still favorable with actinide-loaded salt and that batch size of this v-blender could be increased to a level consistent with efficient production operations for EBR-II spent fuel treatment. One technical challenge that remains for this technology is to mitigate the problem of material retention in the v-blender due to formation of caked patches of salt/zeolite on the inner v-blender walls.

Effect of Bentonite Type on Thermal Conductivity in a HLW Repository

  • Lee, Gi-Jun;Yoon, Seok;Cho, Won-Jin
    • 방사성폐기물학회지
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    • 제19권3호
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    • pp.331-338
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    • 2021
  • Extensive studies have been conducted on thermal conductivity of bentonite buffer materials, as it affects the safety performance of barriers engineered to contain high-level radioactive waste. Bentonite is composed of several minerals, and studies have shown that the difference in the thermal conductivity of bentonites is due to the variation in their mineral composition. However, the specific reasons contributing to the difference, especially with regard to the thermal conductivity of bentonites with similar mineral composition, have not been elucidated. Therefore, in this study, bentonites with significantly different thermal conductivities, but of similar mineral compositions, are investigated. Most bentonites contain more than 60% of montmorillonite. Therefore, it is believed that the exchangeable cations of montmorillonite could affect the thermal conductivity of bentonites. The effect of bentonite type was comparatively analyzed and was verified through the effective medium model for thermal conductivity. Our results show that Ca-type bentonites have a higher thermal conductivity than Na-type bentonites.

Evaluation of Water Suction for Compacted Bentonite Buffer Under Elevated Temperature Conditions

  • Yoon, Seok;Lee, Deuk-Hwan;Cho, Won-Jin;Lee, Changsoo;Cho, Dong-Keun
    • 방사성폐기물학회지
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    • 제20권2호
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    • pp.185-192
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    • 2022
  • A compacted bentonite buffer is a major component of engineered barrier systems, which are designed for the disposal of high-level radioactive waste. In most countries, the target temperature required to maintain safe functioning is below 100℃. If the target temperature of the compacted bentonite buffer can be increased above 100℃, the disposal area can be dramatically reduced. To increase the target temperature of the buffer, it is necessary to investigate its properties at temperatures above 100℃. Although some studies have investigated thermal-hydraulic properties above 100℃, few have evaluated the water suction of compacted bentonite. This study addresses that knowledge gap by evaluating the water suction variation for compacted Korean bentonite in the 25-150℃ range, with initial saturations of 0 and 0.22 under constant saturation conditions. We found that water suction decreased by 5-20% for a temperature increase of 100-150℃.

폐유리발포비드를 혼입한 고강도 시멘트 복합체의 수화 특성 (Hydration Properties of High-strength Cementitious Composites Incorporating Waste Glass Beads)

  • 편수정;김규용;이상수;남정수
    • 한국건설순환자원학회논문집
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    • 제10권1호
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    • pp.74-79
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    • 2022
  • 본 연구에서는 고강도 콘크리트 및 시멘트 복합체의 밀실한 내부 구조로 인한 급격한 내부 습도 저하 및 수화도 저하 등의 영향을 파악하고자 하였다. 내부 Si 수화도 변화 검증을 위해 폐유리발포비드를 경량골재로 사용하였으며, 중장기에 걸쳐 내부 미반응 수화물의 저감 및 수화물 형성 경향을 파악하였다. 폐유리발포비드는 5, 10, 20 % 혼입되었으며 프리웨팅하여 사용하였다. 폐유리발포비드의 혼입률이 증가함에 따라 강도는 감소하는 경향을 보였다. 이와 함께 XRD 분석, TGA 분석 및 Si NMR 분석을 통해 프리웨팅된 폐유리발포비드의 혼입량이 내부에 증가할 때, 페이스트에 수분이 공급되는 것으로 내부 Si의 수화 정도는 달라지는 것으로 판단된다.

Advanced Treatment of Wastewater from Food Waste Disposer in Modified Ludzack-Ettinger Type Membrane Bioreactor

  • Lee, Jae-Woo;Jutidamrongphan, Warangkana;Park, Ki-Young;Moon, Se-Heum;Park, Chul
    • Environmental Engineering Research
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    • 제17권2호
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    • pp.59-63
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    • 2012
  • This paper proposes a modified Ludzack-Ettinger (MLE) type membrane bioreactor (MBR) as a method of treatment for wastewater from food waste disposer. Micro-membrane filtration allows for an extremely low concentration of suspended solids in the effluent. The effluent of the reactor in question is characterized by a relatively high level of non-biodegradable organics, containing a substantial amount of soluble microbial products and biomass. Results obtained in this paper by measurement of membrane fouling are consistent with biomass concentration in the reactor, as opposed to chemical oxygen demand (COD). The MLE process is shown to be effective for the treatment of wastewater with a high COD/N ratio of 20, resulting in are markedly high total nitrogen removal efficiency. Denitrification could be improved at a higher internal recycle ratio. Despite the low concentration of influent phosphorus, the phosphorus concentration of the outflow is seen to be relatively high. This is because outflow phosphorous concentration is related to COD consumption, and the process operates at along solids retention time.