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      고준위폐기물처분장 공학적방벽시스템의 열-수리-역학적 복합거동 해석 모델 개발 현황 = Current Status of the Numerical Models for the Analysis of Coupled Thermal-Hydrological-Mechanical Behavior of the Engineered Barrier System in a High-level Waste Repository

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      https://www.riss.kr/link?id=A101193017

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      다국어 초록 (Multilingual Abstract)

      The current status of the computer codes for the analysis of coupled thermal-hydrological-mechanical behavior occurred in a high-level waste repository was investigated. Based on the reported results on the comparison between the predictions using the computer codes and the experimental data from the in-situ tests, the reliability of the existing computer codes was analyzed. The presented codes simulated considerably well the coupled thermal-hydrological-mechanical behavior in the near-field rock of the repository without buffer, but the predictions for the engineered barrier system of the repository located at saturated hard rock were not satisfactory. To apply the current thermal-hydrological-mechanical models to the assessment of the performance of engineered barrier system, a major improvement on the mathematical models which analyze the distribution of water content and total pressure in the buffer is required.
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      The current status of the computer codes for the analysis of coupled thermal-hydrological-mechanical behavior occurred in a high-level waste repository was investigated. Based on the reported results on the comparison between the predictions using the...

      The current status of the computer codes for the analysis of coupled thermal-hydrological-mechanical behavior occurred in a high-level waste repository was investigated. Based on the reported results on the comparison between the predictions using the computer codes and the experimental data from the in-situ tests, the reliability of the existing computer codes was analyzed. The presented codes simulated considerably well the coupled thermal-hydrological-mechanical behavior in the near-field rock of the repository without buffer, but the predictions for the engineered barrier system of the repository located at saturated hard rock were not satisfactory. To apply the current thermal-hydrological-mechanical models to the assessment of the performance of engineered barrier system, a major improvement on the mathematical models which analyze the distribution of water content and total pressure in the buffer is required.

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      참고문헌 (Reference)

      1 J. Rutqvist, "Thermohydromechanics of partially saturated geological media - Governing equation and formulation of four finite element models" 38 : 105-127, 2001

      2 E.E. Alonso, "The FEBEX benchmark test : case definition and comparison of modelling approaches" 42 : 611-638, 2005

      3 K. Pruess, "TOUGH2 user’s guide, version 2.0" Lawrence Berkeley National Laboratory 1999

      4 A. Gens, "THMC Processes in engineered barriers : Theexperience from Febex and Prototype Projects" 2004

      5 권상기, "THM 복합거동 해석을 위한 DECOVALEX 국제 공동연구 현황" 한국방사성폐기물학회 5 (5): 323-338, 2007

      6 Y. Ohnishi, "THAMES, coupled thermo-hydro-mechanical processes of fractured media, In Developments in geotechinical engineering" Elsevier 545-549, 1996

      7 A.P.S. Selvadurai, "Scoping analyses of the coupled thermal-hydrological-mechanical behaviour of the rock mass around a nuclear fuel waste repository" 47 : 370-400, 1996

      8 J. Rutqvist, "Results from an international study on coupled thermal, hydrological, and mechanical processes near geological nuclear waste repository" 163 : 101-109, 2008

      9 O. Kolditz, "ROCKFLOW - Theory and user manual, release 3.9, Groundwater Group"

      10 Q. Liu, "Practical method for coupled THM simulations of the Yacca Mountain and FEBEX case samples for Task D of the DECOVALEX- THMC Project" HoHai University 220-225, 2006

      1 J. Rutqvist, "Thermohydromechanics of partially saturated geological media - Governing equation and formulation of four finite element models" 38 : 105-127, 2001

      2 E.E. Alonso, "The FEBEX benchmark test : case definition and comparison of modelling approaches" 42 : 611-638, 2005

      3 K. Pruess, "TOUGH2 user’s guide, version 2.0" Lawrence Berkeley National Laboratory 1999

      4 A. Gens, "THMC Processes in engineered barriers : Theexperience from Febex and Prototype Projects" 2004

      5 권상기, "THM 복합거동 해석을 위한 DECOVALEX 국제 공동연구 현황" 한국방사성폐기물학회 5 (5): 323-338, 2007

      6 Y. Ohnishi, "THAMES, coupled thermo-hydro-mechanical processes of fractured media, In Developments in geotechinical engineering" Elsevier 545-549, 1996

      7 A.P.S. Selvadurai, "Scoping analyses of the coupled thermal-hydrological-mechanical behaviour of the rock mass around a nuclear fuel waste repository" 47 : 370-400, 1996

      8 J. Rutqvist, "Results from an international study on coupled thermal, hydrological, and mechanical processes near geological nuclear waste repository" 163 : 101-109, 2008

      9 O. Kolditz, "ROCKFLOW - Theory and user manual, release 3.9, Groundwater Group"

      10 Q. Liu, "Practical method for coupled THM simulations of the Yacca Mountain and FEBEX case samples for Task D of the DECOVALEX- THMC Project" HoHai University 220-225, 2006

      11 J. Rutqvist, "Numerical study of the THM effects on the near-field safety of a hypothetical nuclear waste repository - BMT1 of the DECOVALEX III project. Part 3: Effects of THM coupling in fractured rock" 42 : 745-755, 2005

      12 M. Chijimatsu, "Numerical study of the THM effects on the near-field safety of a hypothetical nuclear waste repository - BMT1 of the DECOVALEX III project. Part 1: Conceptualization and characterization of the problems and summary of the results" 42 : 720-730, 2005

      13 S. Olivella, "Numerical formulation for a simulator ‘CODE_BRIGHT’ for the coupled analysis of saline media" 13 : 87-112, 1996

      14 H.R. Thomas, "Modelling the behaviour of unsaturated soil using an elastic constitutive relationship" 48 : 589-603, 1998

      15 P.J. Cleall, "Modelling in the three-dimensional behaviour ofa prototype nuclear waste repository" 85 : 212-220, 2006

      16 H.J. Choi, "Korean reference HLW disposal system" Korea Atomic Energy Research Institute 2008

      17 H.R. Thomas, "Inclusion of extensive clay behavior in coupled thermo hydraulic mechanical models" 54 : 93-108, 1999

      18 T.S. Nguyen, "Hydro-mechanical response of a fractured rock mass to excavation of a test pit - the Kamaishi mine experiment in Japan" 38 : 78-94, 2001

      19 A,M. Fernández, "Geochemical processes in the FEBEX bentonite after a heating and hydration in situ test in the Grimsel URL" 727-728, 2010

      20 C. Andersson, "Full-scale testing of the KBS- 3V concept for the geological disposal of high-level eadioactive waste, Prototype Repository" 2005

      21 Itasca Consulting Group, "FLAC-Fast Lagrangian analysis of continua, version 4.0"

      22 G.J. Chen, "Coupled thermohydromechanical modelling of the full-scale in situ test Prototype Repository" 135 : 121-132, 2009

      23 J. Rutqvist, "Coupled thermal-hydrological-mechanical analyses of the Yucca Mountain Drift Scale Test - Comparison of field measurements to prediction of four different numerical models" 42 : 680-697, 2005

      24 R. Pusch, "Comparison of results from THMCB modelling of buffer, backfill and rock with measured data from Prototype Repository" 2004

      25 J. Rutqvist, "Analysis of thermalhydrologic- mechanical behavior near as emplacement drift at Yacca Mountain" 62 (62): 637-652, 2003

      26 CEA, "An objective oriented finite element method framework"

      27 A. Gens, "A full-scale in situ heating test for highlevel nuclear waste disposal: observation, analysis and interpretation" 59 : 377-399, 2009

      28 J. Rutqvist, "A comparative simulation study of coupled THM processes and their effect on fractured rock permeability around nuclear waste repositories" 57 : 1347-1360, 2009

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      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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      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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