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      KCI등재 SCIE SCOPUS

      An intelligent hybrid methodology of on-line system-level fault diagnosis for nuclear power plant

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      https://www.riss.kr/link?id=A106056894

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      다국어 초록 (Multilingual Abstract)

      To assist operators to properly assess the current situation of the plant, accurate fault diagnosis methodologyshould be available and used. A reliable fault diagnosis method is beneficial for the safety ofnuclear power plants. The major idea proposed...

      To assist operators to properly assess the current situation of the plant, accurate fault diagnosis methodologyshould be available and used. A reliable fault diagnosis method is beneficial for the safety ofnuclear power plants. The major idea proposed in this work is integrating the merits of different faultdiagnosis methodologies to offset their obvious disadvantages and enhance the accuracy and credibilityof on-line fault diagnosis. This methodology uses the principle component analysis-based model andmulti-flow model to diagnose fault type. To ensure the accuracy of results from the multi-flow model, amechanical simulation model is implemented to do the quantitative calculation. More significantly,mechanism simulation is implemented to provide training data with fault signatures. Furthermore, oneof the distance formulas in similarity measurementdMahalanobis distancedis applied for on-line failuredegree evaluation. The performance of this methodology was evaluated by applying it to the reactorcoolant system of a pressurized water reactor. The results of simulation analysis show the effectivenessand accuracy of this methodology, leading to better confidence of it being integrated as a part of thecomputerized operator support system to assist operators in decision-making.

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      참고문헌 (Reference)

      1 박상준, "Transient Diagnosis and Prognosis for Secondary System in Nuclear Power Plants" 한국원자력학회 48 (48): 1184-1191, 2016

      2 Idaho National Laboratory, "Report from the Light Water Reactor Sustainability Workshop on On-line Monitoring Technologies, INL/EXT-10-19500" 2010

      3 M. Lind, "Reasoning about causes and consequences in multilevel flow models" ESREL 2359-2367, 2011

      4 A. Herve, "Principal component analysis" 2 (2): 433-459, 2010

      5 Y.Q. Wang, "Online monitoring the incore power distribution by using excore ion-chambers" 225 (225): 15-32, 2003

      6 B. Lu, "Monitoring and fault diagnosis of the steam generator system of a nuclear power plant using data-driven modeling and residual space analysis" 32 : 897-912, 2005

      7 Akio Gofuku, "Integrated Diagnostic Technique for Nuclear Power Plants" 한국원자력학회 46 (46): 725-736, 2014

      8 Y.-K. Liu, "Improvement of fault diagnosis efficiency in nuclear power plants using hybrid intelligence approach" 76 (76): 122-136, 2014

      9 H. Wang, "Improved methods of online monitoring and prediction in condensate and feed water system of nuclear power plant" 90 (90): 44-53, 2016

      10 R. Dunia, "Identification of faulty sensors using principal component analysis" 42 (42): 2797-2812, 1996

      1 박상준, "Transient Diagnosis and Prognosis for Secondary System in Nuclear Power Plants" 한국원자력학회 48 (48): 1184-1191, 2016

      2 Idaho National Laboratory, "Report from the Light Water Reactor Sustainability Workshop on On-line Monitoring Technologies, INL/EXT-10-19500" 2010

      3 M. Lind, "Reasoning about causes and consequences in multilevel flow models" ESREL 2359-2367, 2011

      4 A. Herve, "Principal component analysis" 2 (2): 433-459, 2010

      5 Y.Q. Wang, "Online monitoring the incore power distribution by using excore ion-chambers" 225 (225): 15-32, 2003

      6 B. Lu, "Monitoring and fault diagnosis of the steam generator system of a nuclear power plant using data-driven modeling and residual space analysis" 32 : 897-912, 2005

      7 Akio Gofuku, "Integrated Diagnostic Technique for Nuclear Power Plants" 한국원자력학회 46 (46): 725-736, 2014

      8 Y.-K. Liu, "Improvement of fault diagnosis efficiency in nuclear power plants using hybrid intelligence approach" 76 (76): 122-136, 2014

      9 H. Wang, "Improved methods of online monitoring and prediction in condensate and feed water system of nuclear power plant" 90 (90): 44-53, 2016

      10 R. Dunia, "Identification of faulty sensors using principal component analysis" 42 (42): 2797-2812, 1996

      11 Morten Lind, "Functional Modelling for Fault Diagnosis and its Application for NPP" 한국원자력학회 46 (46): 753-772, 2014

      12 K. Hadad, "Fault diagnosis and classification based on wavelet transform and neural network" 53 (53): 41-47, 2011

      13 A.C. Cilliers, "Fault detection and characterisation in Pressurized Water Reactors using real-time simulations" 38 : 1196-1205, 2011

      14 X. Li, "Evidence supporting measure of similarity for reducing the complexity in information fusion" 181 (181): 1818-1835, 2011

      15 A. Gofuku, "Diagnostic techniques of a small-break loss-of-coolant accident at a pressurized water reactor plant" 81 : 313-332, 1988

      16 IAEA, "Diagnostic and Prognostic Techniques in Monitoring Structures, Systems and Components in Nuclear Power Plants, No.NP-T-3.14" 2013

      17 H.C. Soon, "Development of the on-line operator aid system OASYS using a rule-based expert system and fuzzy logic for nuclear power plants" 112 : 266-294, 1995

      18 O. Shigetoshi, "Development and Application of the Plant Condition Monitoring System for Nuclear Power Plants" 2013

      19 S.J. Qin, "Determining the number of principal components for best reconstruction" 10 (10): 245-250, 2000

      20 Y.Y. Chu, "Design of an operator support system for online maintenance at nuclear power Plant" 2011

      21 A.C. Cilliers, "Correlating hardware fault detection information from distributed control systems to isolate and diagnose a fault in pressurized water reactors" 54 (54): 91-103, 2013

      22 X.X. Zhang, "Consequence reasoning in multilevel flow modelling" 187-194, 2013

      23 J. Ma, "Applications of fault detection and diagnosis methods in nuclear power plants: a review" 53 (53): 255-266, 2011

      24 T.V. Santosh, "Application of artificial neural networks to nuclear power plant transient diagnosis" 92 (92): 1468-1472, 2007

      25 P.M. Frank, "Analytical and qualitative model-based fault diagnosis - a survey and some new results" 2 (2): 6-28, 1996

      26 E. Zio, "An extended classifiability index for feature selection in nuclear transients" 32 (32): 1632-1649, 2005

      27 K. Zhao, "An Integrated Approach to Performance Monitoring and Fault Diagnosis of Nuclear Power Systems" University of Tennessee 2005

      28 K. Thomas, "A Computerized Operator Support System Prototype, INL/EXT-15-36788" Idaho National Laboratory 2015

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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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