• 제목/요약/키워드: High Level Nuclear Waste

검색결과 240건 처리시간 0.024초

Extraction behaviors of platinum group metals in simulated high-level liquid waste by a hydrophobic ionic liquid bearing an amino moiety

  • Wu, Hao;Kim, Seong-Yun;Takahashi, Tadayuki;Oosugi, Haruka;Ito, Tatsuya;Kanie, Kiyoshi
    • Nuclear Engineering and Technology
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    • 제53권4호
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    • pp.1218-1223
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    • 2021
  • A hydrophobic ionic liquid including an amino moiety ([DiOcAPmim][NTf2]) was synthesized. Its extraction behaviors towards Pd(II), Ru(III), Rh(III) were investigated in nitric acid aqueous solution as a function of contact time, effect of concentration of nitric acid, effect of temperature, and effect of co-existing metal ions. The extraction kinetics of Pd(II) was fairly fast and extraction equilibrium can be attained within only 5 min under the [HNO3] = 2.05 M. When [HNO3]< 1 M, the extraction percentage of Pd(II), Ru(III), Rh(III) were all above 80%. When [HNO3] reached 2 M, all of the extraction percentage decreased and in an order of Pd(II)>Ru(III)>Rh(III). When [HNO3]> 2 M, the extraction performance gradually recovered. The effect of temperature can slightly affect the extraction performance of Pd(II). Furthermore, in simulated high-level liquid waste, [DiOcAPmim][NTf2] showed a better preference towards Pd(II) under the interference of various other co-existing metal ions.

Hydraulic Conductivity of Bentonite-Sand Mixture for a Potential Backfill Material for a High-level Radioactive Waste Repository

  • Cho, Won-Jin;Lee, Jae-Owan;Kang, Chul-Hyung
    • Nuclear Engineering and Technology
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    • 제32권5호
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    • pp.495-503
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    • 2000
  • The hydraulic conductivities in the bentonite-sand mixtures with high density were measured, and the effects of sand content and dry density on the hydraulic conductivity were investigated. The hydraulic conductivities of the bentonite-sand mixtures with a dry density of 1.6 Mg/㎥ and 1.8 Mg/㎥ are less than 10$^{-11}$ m/s when the sand content is not higher than 70 wt%. However at the sand content of 90 wt%, the hydraulic conductivity increases rapidly At the same dry density, the logarithm of hydraulic conductivity increases linearly with increasing sand content. The hydraulic conductivity of the bentonite-sand mixture can be explained by the concept of effective clay dry density, and using this concept, the hydraulic conductivities for the mixtures with various sand contents and dry densities can be estimated.

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Thermal Influence on Hydraulic Conductivity in Compacted Bentonite: Predictive Modeling Based on the Dry Density-Hydraulic Conductivity Relationship

  • Gi-Jun Lee;Seok Yoon;Won-Jin Cho
    • 방사성폐기물학회지
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    • 제22권1호
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    • pp.17-25
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    • 2024
  • Hydraulic conductivity is a critical design parameter for buffers in high-level radioactive waste repositories. Most employed prediction models for hydraulic conductivity are limited to various types of bentonites, the main material of the buffer, and the associated temperature conditions. This study proposes the utilization of a novel integrated prediction model. The model is derived through theoretical and regression analyses and is applied to all types of compacted bentonites when the relationship between hydraulic conductivity and dry density for each compacted bentonite is known. The proposed model incorporates parameters such as permeability ratio, dynamic viscosity, and temperature coefficient to enable accurate prediction of hydraulic conductivity with temperature. Based on the results obtained, the values are in good agreement with the measured values for the selected bentonites, demonstrating the effectiveness of the proposed model. These results contribute to the analysis of the hydraulic behavior of the buffer with temperature during periods of high-level radioactive waste deposition.

고준위방사성폐기물의 시추공 처분 개념 연구 현황 (The State-of-the Art of the Borehole Disposal Concept for High Level Radioactive Waste)

  • 지성훈;고용권;최종원
    • 방사성폐기물학회지
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    • 제10권1호
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    • pp.55-62
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    • 2012
  • 고준위폐기물 처분과 관련하여, 최근 저장소 형태의 처분장 개념에 대한 대안으로 검토되고 있는 시추공 처분 개념에 대한 연구 현황을 정리하고 시추공 처분 개념의 국내 적용 가능성과 필요한 연구 항목에 대해 논의하였다. 현재 미국과 스웨덴을 중심으로 논의된 시추공 처분 개념은 심부시추공을 설치하여 지하 3 - 5km 구간에 고준위폐기물을 처분하는 것을 의미하며, 현재까지의 연구 결과에 의하면 이 처분 개념은 심부지하수의 층상구조, 작은 규모의 지표시설 등으로 인해 처분 및 비용 효율이 클 것으로 예상된다. 이에 반해 국내에는 축적된 심부 지질 자료가 없어 적용 가능성에 대한 논의할 여지가 없다. 이에 저장소 형태의 처분장 개념에 대한 대안으로 시추공 처분 개념을 검토하기 위해서는 향후 심지층 자료 확보, 공학적 방벽 연구, 수치모의모델 개발, 처분 기술 개발 등의 연구가 필요하다.

고준위방사성폐기물 처분 관련 자료 관리 해외사례 분석 (Analysis of Overseas Data Management Systems for High Level Radioactive Waste Disposal)

  • 김민정;박선주;김혜림;윤운상;박정훈;이정환
    • 지질공학
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    • 제33권2호
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    • pp.323-334
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    • 2023
  • 고준위방사성폐기물 처분을 위한 다양한 조사와 연구를 진행하는 과정에서 막대한 양의 자료가 생산되며 이를 관리하기 위한 자료 관리가 필요하다. 스웨덴의 SKB는 SICADA를 구축하여 부지선정, 평가, 해석, 분석 및 모델링에 활용할 수 있게 하였고, 독일의 BGE는 부지선정법에 따라 자료를 관리하기 위해 데이터베이스 및 문서 관리시스템 ArbeitsDB와 자료시스템 ELO를 구축하였다. 영국의 NWS는 DMS를 구축하여 연구, 조사 자료를 관리할 수 있도록 하였다. 미국의 DOE와 OCRWM은 부지특성화 조사를 진행하면서 자료 관리 및 이후의 인허가 절차를 위하여 TDMS를 구축하였다. 해외사례 조사, 분석을 통해 자료의 품질관리와 자료 활용의 확장성이 자료 관리에 있어 중요한 부분임을 확인할 수 있다. 향후 우리나라도 장기적인 관점에서 자료의 품질관리와 확장성을 고려한 자료 관리 개념을 확립하고 그에 맞춘 자료 관리 시스템 및 체계를 구축해야 할 것이다.

Adsorption behavior of platinum-group metals and Co-existing metal ions from simulated high-level liquid waste using HONTA and Crea impregnated adsorbent

  • Naoki Osawa;Seong-Yun Kim;Masahiko Kubota;Hao Wu;Sou Watanabe;Tatsuya Ito;Ryuji Nagaishi
    • Nuclear Engineering and Technology
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    • 제56권3호
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    • pp.812-818
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    • 2024
  • The volume and toxicity of radioactive waste can be decreased by separating the components of high-level liquid waste according to their properties. An impregnated silica-based adsorbent was prepared in this study by combining N,N,N',N',N",N"-hexa-n-octylnitrilotriacetamide (HONTA) extractant, N',N'-di-n-hexyl-thiodiglycolamide (Crea) extractant, and macroporous silica polymer composite particles (SiO2-P). The performance of platinum-group metals adsorption and separation on prepared (HONTA + Crea)/SiO2-P adsorbent was then assessed together with that of co-existing metal ions by batch-adsorption and chromatographic separation studies. From the batch-adsorption experiment results, (HONTA + Crea)/SiO2-P adsorbent showed high adsorption performance of Pd(II) owing to an affinity between Pd(II) and Crea extractant based on the Hard and Soft Acids and Bases theory. Additionally, significant adsorption performance was observed toward Zr(IV) and Mo(VI). Compared with studies using the Crea extractant, the high adsorption performance of Zr(IV) and Mo(VI) is attributed to the HONTA extractant. As revealed from the chromatographic experiment results, most of Pd(II) was recovered from the feed solution using 0.2 M thiourea in 0.1 M HNO3. Additionally, the possibility of recovery of Zr(IV), Mo(VI), and Re(VII) was observed using the (HONTA + Crea)/SiO2-P adsorbent.

Swelling Pressures of a Potential Buffer Material for High-Level Waste Repository

  • Lee, Jae-Owan;Cho, Won-Jin;Chun, Kwan-Sik
    • Nuclear Engineering and Technology
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    • 제31권2호
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    • pp.139-150
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    • 1999
  • The swelling pressure of a potential buffer material was measured and the effect of dry density, bentonite content and initial water content on the swelling pressure was investigated to provide the information for the selection of buffer material in a high-level waste repository. Swelling tests were carried out according to Box-Behnken's experimental design. Measured swelling pressures were in the wide range of 0.7 Kg/$\textrm{cm}^2$ to 190.2 Kg/$\textrm{cm}^2$ under given experimental conditions. Based upon the experimental data, a 3-factor polynomial swelling model was suggested to analyze the effect of dry density, bentonite content and initial water content on the swelling pressure The swelling pressure increased with an increase in the dry density and bentonite content, while it decreased with increasing the initial water content and, beyond about 12 wt.% of the initial water content, levelled off to nearly constant value.

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Analysis of Functional Criteria for Buffer Material in a High-level Radioactive Waste Repository

  • W. J. Cho;Lee, J. O.;K. S. Chun;Park, Hyun-Soo
    • Nuclear Engineering and Technology
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    • 제31권1호
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    • pp.116-132
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    • 1999
  • This study is intended to analyze the requirements of a buffer material that is one of the major components of the engineered barriers in a high-level radioactive waste repository. The characteristics of potential materials for the buffer in the repository were analyzed and a candidate material was selected. And, based on the current knowledge and the information from various sources, the requirements of a buffer material were evaluated. Finally its quantitative functional criteria on the generic viewpoint has been recommended to be supplied as a guideline for the development of the reference disposal concept and the related buffer material in Korea. The criteria are composed of seven major items, such as hydraulic conductivity, retardation capacity, swelling potential and swelling pressure, thermal conductivity, longevity, organic matter content, and mechanical properties.

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