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      Review and Strategy for Study on Korean Buffer Characteristics Under the Elevated Temperature Conditions: Mineral Transformation and Radionuclide Retardation Perspective

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      https://www.riss.kr/link?id=A108146481

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      다국어 초록 (Multilingual Abstract)

      In the majority of countries, the upper limit of buffer temperature in a repository is set to below 100℃ due to the possible illitization.
      This smectite-to-illite transformation is expected to be detrimental to the swelling functions of the buffer. However, if the upper limit is increased while preventing illitization, the disposal density and cost-effectiveness for the repository will dramatically increase. Thus, understanding the characteristics and creating a database related to the buffer under the elevated temperature conditions is crucial. In this study, a strategy to investigate the bentonite found in Korea under the elevated temperatures from a mineral transformation and radionuclides retardation perspective was proposed. Certain long-term hydrothermal reactions generated the bentonite samples that were utilized for the investigation of their mineral transformation and radionuclide retardation characteristics. The bentonite samples are expected to be studied using in-situ synchrotron-based X-Ray Diffraction (XRD) technique to determine the smectite-to-illite transformation. Simultaneously, the ‘high-temperature and high-pressure mineral alteration measurement system’ based on the Diamond Anvil Cell (DAC) will control and provide the elevated temperature and pressure conditions during the measurements. The kinetic models, including the Huang and Cuadros model, are expected to predict the time and manner in which the illitization will become detrimental to the performance and safety of the repository. The sorption reactions planned for the bentonite samples to evaluate the effects on retardation will provide the information required to expand the current knowledge of repository optimization.
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      In the majority of countries, the upper limit of buffer temperature in a repository is set to below 100℃ due to the possible illitization. This smectite-to-illite transformation is expected to be detrimental to the swelling functions of the buffer. ...

      In the majority of countries, the upper limit of buffer temperature in a repository is set to below 100℃ due to the possible illitization.
      This smectite-to-illite transformation is expected to be detrimental to the swelling functions of the buffer. However, if the upper limit is increased while preventing illitization, the disposal density and cost-effectiveness for the repository will dramatically increase. Thus, understanding the characteristics and creating a database related to the buffer under the elevated temperature conditions is crucial. In this study, a strategy to investigate the bentonite found in Korea under the elevated temperatures from a mineral transformation and radionuclides retardation perspective was proposed. Certain long-term hydrothermal reactions generated the bentonite samples that were utilized for the investigation of their mineral transformation and radionuclide retardation characteristics. The bentonite samples are expected to be studied using in-situ synchrotron-based X-Ray Diffraction (XRD) technique to determine the smectite-to-illite transformation. Simultaneously, the ‘high-temperature and high-pressure mineral alteration measurement system’ based on the Diamond Anvil Cell (DAC) will control and provide the elevated temperature and pressure conditions during the measurements. The kinetic models, including the Huang and Cuadros model, are expected to predict the time and manner in which the illitization will become detrimental to the performance and safety of the repository. The sorption reactions planned for the bentonite samples to evaluate the effects on retardation will provide the information required to expand the current knowledge of repository optimization.

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      참고문헌 (Reference)

      1 박태진, "Thermal behavior of groundwater-saturated Korean buffer under the elevated temperature conditions: In-situ synchrotron X-ray powder diffraction study for the montmorillonite in Korean bentonite" 한국원자력학회 53 (53): 1511-1518, 2021

      2 A. M. Pytte, "Thermal History of Sedimentary Basins" Springer 133-140, 1989

      3 K. Ikonen, "Thermal Condition of Open KBS-3H Tunnel" Posiva Oy 2005

      4 G. R. Simmons, "The Disposal of Canada’s Nuclear Fuel Waste: Engineering for a Disposal Facility" Atomic Energy of Canada Limited 1994

      5 J. K. Lee, "Technology Development for the Performance Demonstration of the Spent Nuclear Fuel Disposal System – Evaluation of Geochemical Behavior of Radionuclides in Multiple Barriers" Korea Atomic Energy Research Institute 2020

      6 Posiva Oy, "Safety Case for the Disposal of Spent Nuclear Fuel at Olkiluoto – Performance Assessment 2012" Posiva Oy 2012

      7 Posiva Oy, "Safety Case for the Disposal of Spent Nuclear Fuel at Olkiluoto – Design Basis 2012" Posiva Oy 2012

      8 W. J. Cho, "Reconsideration of Thermal Criteria for Korean Spent Fuel Repository" 88 : 73-82, 2016

      9 P. Wersin, "Performance of the Bentonite Barrier at Temperatures Beyond 100℃: A Critical Review" 32 (32): 780-788, 2007

      10 L. Zhen, "On the Impact of Temperatures up to 200℃ in Clay Repositories With Bentonite Engineer Barrier Systems : A Study With Coupled Thermal, Hydrological, Chemical, and Mechanical Modeling" 197 : 278-295, 2015

      1 박태진, "Thermal behavior of groundwater-saturated Korean buffer under the elevated temperature conditions: In-situ synchrotron X-ray powder diffraction study for the montmorillonite in Korean bentonite" 한국원자력학회 53 (53): 1511-1518, 2021

      2 A. M. Pytte, "Thermal History of Sedimentary Basins" Springer 133-140, 1989

      3 K. Ikonen, "Thermal Condition of Open KBS-3H Tunnel" Posiva Oy 2005

      4 G. R. Simmons, "The Disposal of Canada’s Nuclear Fuel Waste: Engineering for a Disposal Facility" Atomic Energy of Canada Limited 1994

      5 J. K. Lee, "Technology Development for the Performance Demonstration of the Spent Nuclear Fuel Disposal System – Evaluation of Geochemical Behavior of Radionuclides in Multiple Barriers" Korea Atomic Energy Research Institute 2020

      6 Posiva Oy, "Safety Case for the Disposal of Spent Nuclear Fuel at Olkiluoto – Performance Assessment 2012" Posiva Oy 2012

      7 Posiva Oy, "Safety Case for the Disposal of Spent Nuclear Fuel at Olkiluoto – Design Basis 2012" Posiva Oy 2012

      8 W. J. Cho, "Reconsideration of Thermal Criteria for Korean Spent Fuel Repository" 88 : 73-82, 2016

      9 P. Wersin, "Performance of the Bentonite Barrier at Temperatures Beyond 100℃: A Critical Review" 32 (32): 780-788, 2007

      10 L. Zhen, "On the Impact of Temperatures up to 200℃ in Clay Repositories With Bentonite Engineer Barrier Systems : A Study With Coupled Thermal, Hydrological, Chemical, and Mechanical Modeling" 197 : 278-295, 2015

      11 O. Karnland, "Montmorillonite Stability With Special Respect to KBS-3 Conditions" Swedish Nuclear Fuel and Waste Management Co 2006

      12 S. K. Srivastava, "Microstructural Parameters and Layer Disorder Accompanying Dehydration Transformation in Na-montmorillonite" 215 (215): 235-239, 2000

      13 R. Mosser-Ruck, "Hydrothermal Reactivity of K-smectite at 300℃ and 100 bar : Dissolution-crystallisation Process and non-expandable Dehydrated Smectite Formation" 34 (34): 275-290, 1999

      14 Grimsel Test Site, "High Temperature Effects on Bentonite Buffers (HotBent) –Aims & Objectives. GTS Projects, GTS Phase VI, HotBENT"

      15 Japan Nuclear Cycle Development Institute, "H12: Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan (Supporting Report 2) Repository Design and Engineering Technology" JNC 2000

      16 Grimsel Test Site, "GTS News Letter December 2020 Year 2, Vol. 4" GTS Newsletters

      17 J. Cuadros, "Experimental Kinetic Study of the Smectite-to-illite Transformation" 60 (60): 439-453, 1996

      18 Svensk Kärnbränslehantering AB, "Design Premises for a KBS-3V Repository Based on Results From the Safety Assessment SR-Can and Some Subsequent Analyses" SKB 2009

      19 J. Lee, "Concept of a Korean Reference Disposal System for Spent Fuels" 44 (44): 1565-1573, 2007

      20 T.J. Park, "Buffer Retardation Experiment for Radionuclides Under the Elevated Temperature Conditions:Strategy and Methodology Development for the Korean Bentonite" 16 (16): 203-204, 2018

      21 I. Y. Kim, "Analysis on Characteristics of Reference SNF for KRS+ design – II. KOFA SNF" Korea Atomic Energy Research Institute 2020

      22 I. Y. Kim, "Analysis on Characteristics of Reference SNF for KRS+ Design – I. PLUS7SNF" Korea Atomic Energy Research Institute 2019

      23 W. L. Huang, "An Experimentally Derived Kinetic Model for a Smectite-to-illite Conversion and its use as Geothermometer" 41 (41): 162-177, 1993

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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
      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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