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      SCIE SCOPUS KCI등재

      RISK-INFORMED REGULATION: HANDLING UNCERTAINTY FOR A RATIONAL MANAGEMENT OF SAFETY

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      https://www.riss.kr/link?id=A100955347

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      다국어 초록 (Multilingual Abstract)

      A risk-informed regulatory approach implies that risk insights be used as supplement of deterministic information for safety decision-making purposes. In this view, the use of risk assessment techniques is expected to lead to improved safety and a mor...

      A risk-informed regulatory approach implies that risk insights be used as supplement of deterministic information for safety decision-making purposes. In this view, the use of risk assessment techniques is expected to lead to improved safety and a more rational allocation of the limited resources available. On the other hand, it is recognized that uncertainties affect both the deterministic safety analyses and the risk assessments. In order for the risk-informed decision making process to be effective, the adequate representation and treatment of such uncertainties is mandatory. In this paper, the risk-informed regulatory framework is considered under the focus of the uncertainty issue. Traditionally, probability theory has provided the language and mathematics for the representation and treatment of uncertainty. More recently, other mathematical structures have been introduced. In particular, the Dempster-Shafer theory of evidence is here illustrated as a generalized framework encompassing probability theory and possibility theory. The special case of probability theory is only addressed as term of comparison, given that it is a well known subject. On the other hand, the special case of possibility theory is amply illustrated. An example of the combination of probability and possibility for treating the uncertainty in the parameters of an event tree is illustrated.

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      참고문헌 (Reference)

      1 IAEA, "informed regulation of nuclear facilities: overview of the current status"

      2 A.P. Dempster, "Upper and Lower Probabilities Induced by a Multivalued Mapping" 38 : 325-339, 1967

      3 A.C. Kadak, "The Nuclear Industry’s Transition to Risk-Informed Regulation and Operation in the United States" 92 : 609-618, 2007

      4 F.R. Farmer, "The Growth of Reactor Safety Criteria in the United Kingdom, Anglo-Spanish Power Symposium" Madrid 1964

      5 G.E. Apostolakis, "The Concept of Probability in Safety Assessments of Technological Systems" 1359-1364, 1990

      6 K.-Y Cai, "System Failure Engineering and Fuzzy Methodology. An Introductory Overview" 83 : 113-133, 1996

      7 Soft Methods in Safety and Reliability, "Special Sessions IIII" 1 : 2007

      8 Da Ruan, "Soft Computing for Risk Evaluation and Management" Physica-Verlag 2001

      9 S. Ferson, "Representation, Propagation and Aggregation of Uncertainty" SAND Report

      10 Garrick, B.J., "Reliability Analysis of Nuclear Power Plant Protective Systems, US Atomic Energy Commission"

      1 IAEA, "informed regulation of nuclear facilities: overview of the current status"

      2 A.P. Dempster, "Upper and Lower Probabilities Induced by a Multivalued Mapping" 38 : 325-339, 1967

      3 A.C. Kadak, "The Nuclear Industry’s Transition to Risk-Informed Regulation and Operation in the United States" 92 : 609-618, 2007

      4 F.R. Farmer, "The Growth of Reactor Safety Criteria in the United Kingdom, Anglo-Spanish Power Symposium" Madrid 1964

      5 G.E. Apostolakis, "The Concept of Probability in Safety Assessments of Technological Systems" 1359-1364, 1990

      6 K.-Y Cai, "System Failure Engineering and Fuzzy Methodology. An Introductory Overview" 83 : 113-133, 1996

      7 Soft Methods in Safety and Reliability, "Special Sessions IIII" 1 : 2007

      8 Da Ruan, "Soft Computing for Risk Evaluation and Management" Physica-Verlag 2001

      9 S. Ferson, "Representation, Propagation and Aggregation of Uncertainty" SAND Report

      10 Garrick, B.J., "Reliability Analysis of Nuclear Power Plant Protective Systems, US Atomic Energy Commission"

      11 WASH-1400, "Reactor Safety Study"

      12 C. Baudrit, "Practical Representations of Incomplete Probabilistic Knowledge, Computational Statistics and Data Analysis" 51 : 86-108, 2006

      13 D. Dubois, "Possibility Theory: An Approach to Computerized Processing of Uncertainty" Plenum Press 1988

      14 D. Dubois, "Possibility Theory and Statistical Reasoning" 51 : 47-69, 2006

      15 G. de Cooman, "Possibility Theory Part I : Measure- and Integral-Theoretic Groundwork; Part II: Conditional Possibility; Part III: Possibilistic Independence" 25 (25): 291-371, 1997

      16 R. Yager, "On the Dempster-Shafer Framework and New Combination Rules" 16 : 37-41,

      17 Tao Yuan, "Nuclear Power Plant 2 Operating Living PRA Report (Draft)" Nuclear Energy Research Center 1995

      18 M.H.Kalos,P.A, "Monte Carlo methods" Basics 1986

      19 R.E. Moore, "Methods and Applications of Interval Analysis" SIAM 1979

      20 C. Baudrit, "Joint Propagation of Probabilistic and Possibilistic Information in Risk Assessment" 14 : 593-608, 2006

      21 G.J. Klir, "Fuzzy Sets and Fuzzy Logic: Theory and Applications, Upper Saddle River" Prentice-Hall 1995

      22 L.A. Zadeh, "Fuzzy Sets" 8 : 338-353, 1965

      23 K. Sentz, "Combination of Evidence in Dempster-Shafer Theory" Sandia National Laboratories 2002

      24 U.S. Nuclear Regulatory Commission Regulatory Guide 1, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Current Licensing Basis"

      25 U.S. Nuclear Regulatory Commission Regulatory Guide 1.177, "An Approach for Plant-Specific, Risk-Informed Decisionmaking: Technical Specifications" USNRC 1998

      26 U.S. Nuclear Regulatory Commission Regulatory Guide 1.175, "An Approach for Plant-Specific, Risk-Informed Decisionmaking: Inservice Testing" USNRC 1998

      27 U.S. Nuclear Regulatory Commission Regulatory Guide 1.176, "An Approach for Plant-Specific, Risk-Informed Decisionmaking: Graded Quality Assurance" USNRC 1998

      28 J.C. Helton, "Alternative Representations of Epistemic Uncertainty" 85 : 2004

      29 M. Modarres, "Advanced Nuclear Power Plant Regulation Using Risk-Informed and Performance-Based Methods, Reliability Engineering and System Safety"

      30 D. Huang, "A fuzzy set approach for event tree analysis" pp 153-165 118 : 153-165, 2001

      31 D. Huang, "A fuzzy set approach for event tree analysis" 118 : 153-165, 2001

      32 G. Shafer, "A Mathematical Theory of Evidence" University Press 1976

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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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