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      KCI등재 SCIE SCOPUS

      SCALING ANALYSIS IN BEPU LICENSING OF LWR

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      https://www.riss.kr/link?id=A104203249

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      다국어 초록 (Multilingual Abstract)

      “Scaling” plays an important role for safety analyses in the licensing of water cooled nuclear power reactors. Accident analyses, a sub set of safety analyses, is mostly based on nuclear reactor system thermal hydraulics, and therefore based on an...

      “Scaling” plays an important role for safety analyses in the licensing of water cooled nuclear power reactors. Accident analyses, a sub set of safety analyses, is mostly based on nuclear reactor system thermal hydraulics, and therefore based on an adequate experimental data base, and in recent licensing applications, on best estimate computer code calculations. In the field of nuclear reactor technology, only a small set of the needed experiments can be executed at a nuclear power plant; the major part of experiments, either because of economics or because of safety concerns, has to be executed at reduced scale facilities.
      How to address the scaling issue has been the subject of numerous investigations in the past few decades (a lot of work has been performed in the 80thies and 90thies of the last century), and is still the focus of many scientific studies. The present paper proposes a “roadmap” to scaling. Key elements are the “scaling-pyramid”, related “scaling bridges” and a logical path across scaling achievements (which constitute the “scaling puzzle”). The objective is addressing the scaling issue when demonstrating the applicability of the system codes, the “key-to-scaling”, in the licensing process of a nuclear power plant.
      The proposed “road map to scaling” aims at solving the “scaling puzzle”, by introducing a unified approach to the problem.

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      참고문헌 (Reference)

      1 186 (186): 1998

      2 119 (119): 1990

      3 L.S. Tong, "Thermal Analysis of Pressurized Water Reactors" ANS La Grange Park 1996

      4 M. Ishii, "The three-level scalingapproach with application to the Purdue University Multi-Dimensional IntegralTest Assembly (PUMA)" 186 : 177-211, 1989

      5 N. Zuber, "The effects of complexity, of simplicity and of scaling in thermalhydraulics" 204 : 1-27, 2001

      6 H.Ninokata, "Sub-channel Analysis in Nuclear Reactors" AESJ, Institute of Applied Energy 1-301, 1992

      7 A.N. Navahandi, "Scaling laws for modeling nuclear reactor systems" 72 : 75-83, 1982

      8 S. Banerjee, "Scaling in the safety of next generation reactors" 186 : 111-133, 1998

      9 F. D'Auria, "Scaling in Nuclear Reactor System Thermal Hydraulics" 240 : 3266-3293, 2010

      10 F. D'Auria, "Proposed set of criteria in designing nuclear power plants experimental simulators" 1985

      1 186 (186): 1998

      2 119 (119): 1990

      3 L.S. Tong, "Thermal Analysis of Pressurized Water Reactors" ANS La Grange Park 1996

      4 M. Ishii, "The three-level scalingapproach with application to the Purdue University Multi-Dimensional IntegralTest Assembly (PUMA)" 186 : 177-211, 1989

      5 N. Zuber, "The effects of complexity, of simplicity and of scaling in thermalhydraulics" 204 : 1-27, 2001

      6 H.Ninokata, "Sub-channel Analysis in Nuclear Reactors" AESJ, Institute of Applied Energy 1-301, 1992

      7 A.N. Navahandi, "Scaling laws for modeling nuclear reactor systems" 72 : 75-83, 1982

      8 S. Banerjee, "Scaling in the safety of next generation reactors" 186 : 111-133, 1998

      9 F. D'Auria, "Scaling in Nuclear Reactor System Thermal Hydraulics" 240 : 3266-3293, 2010

      10 F. D'Auria, "Proposed set of criteria in designing nuclear power plants experimental simulators" 1985

      11 F.D'Auria, "Planning of counterpart tests in LWR experimental simulators" 1988

      12 D'Auria, F, "Outline of the uncertainty methodology based on accuracy extrapolation (UMAE)" 109 (109): 21-38, 1995

      13 S. Yokobori, "Optimized apportion between large-scale nuclear thermal-hydraulic tests and simulation" 27 : 461-468, 2008

      14 E. Buckingham, "On physically similar systems; illustrations of the use of dimensional equations" 4 : 345-376, 1914

      15 N.E. Todreas, "Nuclear Systems" Hemisphere Publishing Corp 1990

      16 Y.A. Hassan, "New-wall modeling for complex flows usingthe large eddy simulation technique in curvilinear coordinates" 44 (44): 4009-4026, 2001

      17 R.C. Borges, "Independent qualification of the CIAU based on the uncertainty estimate through the simulation of LOBItest BT-02" 68 (68): 7-16, 2003

      18 N. Zuber, "Evolution of Scale-up Capabilities of Best Estimate Codes" 119 : 97-109, 1990

      19 F.D'Auria, "Assessment of scaling criteria adopted in designing nuclear power plants experimental simulators" 130-, 1985

      20 N. Zuber, "Application of fractional scalinganalysis (FSA) to loss of coolant accidents (LOCA),) - Part 3. Componentlevel scaling for peak clad temperature" 2005

      21 N. Zuber, "Application of fractional scalinganalysis (FSA) to loss of coolant accidents (LOCA) - Part 1: Methodology development" 2005

      22 W. Wulff, "Application of Fractional ScalingAnalysis (FSA) to Loss of Coolant Accidents (LOCA) - Part 2: System Level Scaling for System Depressurization" 2005

      23 N.Zuber, "An integrated structure and scaling methodology for severe accident technical issue resolution: development of methodology" 186 : 1-21, 1998

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      공동연구자 (7)

      유사연구자 (20) 활용도상위20명

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      학술지 이력

      학술지 이력
      연월일 이력구분 이력상세 등재구분
      2023 평가예정 해외DB학술지평가 신청대상 (해외등재 학술지 평가)
      2020-01-01 평가 등재학술지 유지 (해외등재 학술지 평가) KCI등재
      2014-01-01 평가 SCIE 등재 (등재유지) KCI등재
      2014-01-01 평가 SCOPUS 등재 (등재유지) KCI등재
      2011-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2009-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2007-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2006-07-31 학술지명변경 한글명 : Jorunal of the Korean Nuclear Society -> Nuclear Engineering and Technology
      외국어명 : 미등록 -> Nuclear Engineering and Technology
      KCI등재후보
      2004-01-01 평가 등재후보학술지 선정 (신규평가) KCI등재후보
      2003-01-01 평가 등재후보 1차 PASS (등재후보1차) KCI등재후보
      2002-01-01 평가 등재후보학술지 유지 (등재후보1차) KCI등재후보
      1999-01-01 평가 등재후보학술지 선정 (신규평가) KCI등재후보
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      학술지 인용정보

      학술지 인용정보
      기준연도 WOS-KCI 통합IF(2년) KCIF(2년) KCIF(3년)
      2016 1.04 0.17 0.77
      KCIF(4년) KCIF(5년) 중심성지수(3년) 즉시성지수
      0.63 0.56 0.343 0.11
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