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Quantification of Plant Safety Status

Cho, Joo-Hyun   (Korea Atomic Energy Research InstituteCC0186830  ); Lee, Gi-Won   (Korea Atomic Energy Research InstituteCC0186830  ); Kwon, Jong-Soo   (Korea Atomic Energy Research InstituteCC0186830  ); Park, Seong-Hoon   (Korea Atomic Energy Research InstituteCC0186830  ); Na, Young-Whan   (Korea Atomic Energy Research InstituteCC0186830  );
  • 초록

    In the process of simplifying the complex fate of the plant into a binary state, the information loss is inevitable. To minimize the information loss, the quantification of plant safety status has been formulated through the combination of the probability density function arising from the sensor measurement and the membership function representing the expectation of the state of the system. Therefore, in this context, the safety index is introduced in an attempt to quantify the plant status from the perspective of safety. The combination of probability density function and membership function is achieved through the integration of the fuzzy intersection of the two functions, and it often is not a simple task to integrate the fuzzy intersection due to the complexity that is the result of the fuzzy intersection. Therefore, a methodology based on the Algebra of Logic is used to express the fuzzy intersection and the fuzzy union of the arbitrary functions analytically. These exact analytical expressions are then numerically integrated by the application of Monte Carlo method. The benchmark tests for rectangular area and both fuzzy intersection and union of two normal distribution functions have been performed. Lastly, the safety index was determined for the Core Reactivity Control of Yonggwang 3&4 using the presented methodology.


  • 참고문헌 (10)

    1. Measurement Channel Performance Uncertainties (Normal & Accident) for Process Instrumentation for YGN 3&4, Rev.00, 10487-IC-RC870-03, CE-KAERI / v.,pp.,
    2. Determination of Safety Index Using Fuzzy Theory , J.H. Cho(et al.) , Proceedings of the KNS Spring Meeting / v.,pp.227,
    3. Synthesis of Insightful Algorithms , G.W. Lee , Ph.D. Thesis / v.,pp.,
    4. Boron Dilution Alarm System Uncertatinties for YGN 3&4, Rev.00, 10487-IC-RC870-09, CE-KAERI / v.,pp.,
    5. M.H. Ragheb , Lecture Notes on Monte Carlo Simulation / v.,pp.,
    6. COLSS Measurement Channel Uncertatinties for YGN 3&4, Rev.00, 10487-IC-RC870-01, CE-KAERI / v.,pp.,
    7. Design Requirements for the Critical Function Monitoring System for YGN 3&4, Rev.05, 10487-FS-DR210-X, CE-KAERI / v.,pp.,
    8. Plant Data Acquisition System Input Hardware Uncertatinties Calculation for YGN 3&4, Rev.00, 10487-IC-RC712-01, CE-KAERI / v.,pp.,
    9. U.S. NRC , Standard Review Plan : Section 18.2 Safety Parameter Display System (SPDS), Rev.00, NUREG-75/087 / v.,pp.,
    10. G.H. Lee;G.R. Oh , Fuzzy Theory and Application / v.,pp.,

 저자의 다른 논문

  • Cho, Joo-Hyun (2)

    1. 1994 "핵연료 건전성 점검을 위한 감마선 스펙트럼의 자동 분석" Journal of the Korean Nuclear Society = 원자력학회지 26 (4): 555~561    
    2. 1995 "원자력과 화력 발전소간의 에너지 비교 분석" Journal of the Korean Nuclear Society = 원자력학회지 27 (3): 403~417    
  • Lee, Ki-Won (2)

  • 권종수 (1)

  • 박성훈 (1)

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