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      환원환경에서 암반 균열을 통한 우라늄 이동 및 지연 특성 = Migration and Retardation Properties of Uranium through a Rock Fracture in a Reducing Environment

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      https://www.riss.kr/link?id=A101192866

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      다국어 초록 (Multilingual Abstract)

      In this study, uranium migration experiments have been performed using a natural groundwater and a granite core with natural fractures in a glove-box constructed to simulate an appropriate subsurface environment. Groundwater flow experiments using the non-sorbing anionic tracer Br were carried out to analyze the flow properties of groundwater through the fracture of the granite core. The result of the uranium migration experiment showed a breakthrough curve similar to that of the non-sorting Br. This result may imply that uranium migrates as anionic complexes through the rock fracture since uranium can form carbonate complexes at a given groundwater condition. The distribution coefficient $K_d$ of the uranium between the groundwater and the fracture filling material was obtained as low as 2.7 mL/g from a batch sorption experiment. This result agrees well with the result from the migration experiment, showing a faster elution of the uranium through the rock fracture. In order to analyze retardation properties of the uranium through the rock fracture, the retardation factor $R_d({\sim}16.2)$ was obtained by using the $K_d$ obtained from the batch sorption experiment and it was compared with the $R_d({\sim}14.3)$ obtained by using the result from the uranium migration experiment. The values obtained from the both experiments were very similar to each other. This reveals that the retardation of the uranium is mainly occurred by the fracture filling material when the uranium migrates through the fracture of a granite core.
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      In this study, uranium migration experiments have been performed using a natural groundwater and a granite core with natural fractures in a glove-box constructed to simulate an appropriate subsurface environment. Groundwater flow experiments using the...

      In this study, uranium migration experiments have been performed using a natural groundwater and a granite core with natural fractures in a glove-box constructed to simulate an appropriate subsurface environment. Groundwater flow experiments using the non-sorbing anionic tracer Br were carried out to analyze the flow properties of groundwater through the fracture of the granite core. The result of the uranium migration experiment showed a breakthrough curve similar to that of the non-sorting Br. This result may imply that uranium migrates as anionic complexes through the rock fracture since uranium can form carbonate complexes at a given groundwater condition. The distribution coefficient $K_d$ of the uranium between the groundwater and the fracture filling material was obtained as low as 2.7 mL/g from a batch sorption experiment. This result agrees well with the result from the migration experiment, showing a faster elution of the uranium through the rock fracture. In order to analyze retardation properties of the uranium through the rock fracture, the retardation factor $R_d({\sim}16.2)$ was obtained by using the $K_d$ obtained from the batch sorption experiment and it was compared with the $R_d({\sim}14.3)$ obtained by using the result from the uranium migration experiment. The values obtained from the both experiments were very similar to each other. This reveals that the retardation of the uranium is mainly occurred by the fracture filling material when the uranium migrates through the fracture of a granite core.

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      참고문헌 (Reference)

      1 "소규모 지하처분연구시설 부지조사 및 평가" 2004

      2 "방사성폐기물처분연구를 위한 유성지역 화강암내 심부 시추공 단열충전광물의 광물학적 특성" 7 (7): 99-114, 2004

      3 "고준위폐기물 한국형처분시스템 개념설계 요건" 2004

      4 "Uranium(VI) sorption onto selected mineral surfaces: Key geochemical parameters" Academic Press, San Diego 1998

      5 "Update on the Chemical Thermodynamics of Uranium, Neptunium, Plutonium, Americium and Technetium" Elsevier, Amsterdam 2003

      6 "U(VI)의 화강암 수착에 대한 매개변수적 연구" 2 (2): 135-143, 2004

      7 "Tracer movement in a single fissure in granitic rock" 849-858, 1982

      8 "Swedish-German actinide migration experiment at Aspo¨ hard rock laboratory" 61 : 219-233, 2003

      9 "Surface and bulk sorption experiments of U(VI) onto granite rock" 256 : 11-18, 2003

      10 "Speciation and solubility of major actinides under the deep groundwater conditions of Korea" 34 : 517-531, 2002

      1 "소규모 지하처분연구시설 부지조사 및 평가" 2004

      2 "방사성폐기물처분연구를 위한 유성지역 화강암내 심부 시추공 단열충전광물의 광물학적 특성" 7 (7): 99-114, 2004

      3 "고준위폐기물 한국형처분시스템 개념설계 요건" 2004

      4 "Uranium(VI) sorption onto selected mineral surfaces: Key geochemical parameters" Academic Press, San Diego 1998

      5 "Update on the Chemical Thermodynamics of Uranium, Neptunium, Plutonium, Americium and Technetium" Elsevier, Amsterdam 2003

      6 "U(VI)의 화강암 수착에 대한 매개변수적 연구" 2 (2): 135-143, 2004

      7 "Tracer movement in a single fissure in granitic rock" 849-858, 1982

      8 "Swedish-German actinide migration experiment at Aspo¨ hard rock laboratory" 61 : 219-233, 2003

      9 "Surface and bulk sorption experiments of U(VI) onto granite rock" 256 : 11-18, 2003

      10 "Speciation and solubility of major actinides under the deep groundwater conditions of Korea" 34 : 517-531, 2002

      11 "Significance of actinide chemistry for the long-term safety of waste disposal" 38 (38): 459-482, 2006

      12 "In situ tracer tests to determine retention properties of a block sclae fracture network in granitic rock at the Aspo¨ Hard Rock Laboratory" 70 : 271-297, 2004

      13 "In situ resin impregnation for investigating radionuclide retardation in fractured repository host rocks" 35 : 115-130, 1998

      14 "Contribution of minerals to the sorption of U(VI) on granite" 92 : 663-669, 2004

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      학술지 이력

      학술지 이력
      연월일 이력구분 이력상세 등재구분
      2024 평가예정 해외DB학술지평가 신청대상 (해외등재 학술지 평가)
      2021-07-28 학술지명변경 한글명 : 방사성폐기물학회지 -> Journal of Nuclear Fuel Cycle and Waste Technology KCI등재
      2021-01-01 평가 등재학술지 유지 (해외등재 학술지 평가) KCI등재
      2020-01-01 평가 등재학술지 유지 (재인증) KCI등재
      2017-01-01 평가 등재학술지 유지 (계속평가) KCI등재
      2014-08-07 학술지명변경 외국어명 : Journal of Nuclear Fuel Cycle and Waste Technology (Korean) -> Journal of Nuclear Fuel Cycle and Waste Technology KCI등재
      2013-11-26 학술지명변경 외국어명 : Journal of the Korean Radioactive Waste Society -> Journal of Nuclear Fuel Cycle and Waste Technology (Korean) KCI등재
      2013-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2010-01-01 평가 등재학술지 선정 (등재후보2차) KCI등재
      2009-01-01 평가 등재후보 1차 PASS (등재후보1차) KCI등재후보
      2008-01-01 평가 등재후보학술지 유지 (등재후보1차) KCI등재후보
      2006-01-01 평가 등재후보학술지 선정 (신규평가) KCI등재후보
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      학술지 인용정보

      학술지 인용정보
      기준연도 WOS-KCI 통합IF(2년) KCIF(2년) KCIF(3년)
      2016 0.17 0.17 0.17
      KCIF(4년) KCIF(5년) 중심성지수(3년) 즉시성지수
      0.15 0.16 0.409 0.08
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