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Concept of an intelligent operator support system for initial emergency responses in nuclear power plants

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초록

Nuclear power plant operators in the main control room are exposed to stressful conditions in emergency situations as immediate and appropriate mitigations are required. While emergency operating procedures (EOPs) provide operators with the appropriate tasks and diagnostic guidelines, EOPs have static properties that make it difficult to reflect the dynamic changes of the plant. Due to this static nature, operator workloads increase because unrelated information must be screened out and numerous displays must be checked to obtain the plant status. Generally, excessive workloads should be reduced because they can lead to human errors that may adversely affect nuclear power plant safety. This paper presents a framework for an operator support system that can substitute the initial responses of the EOPs, or in other words the immediate actions and diagnostic procedures, in the early stages of an emergency. The system assists operators in emergency operations as follows: performing the monitoring tasks in parallel, identifying current risk and latent risk causality, diagnosing the accident, and displaying all information intuitively with a master logic diagram. The risk causalities are analyzed with a functional modeling methodology called multilevel flow modeling. This system is expected to reduce workloads and the time for performing initial emergency response procedures.

Abstract

Nuclear power plant operators in the main control room are exposed to stressful conditions in emergency situations as immediate and appropriate mitigations are required. While emergency operating procedures (EOPs) provide operators with the appropriate tasks and diagnostic guidelines, EOPs have static properties that make it difficult to reflect the dynamic changes of the plant. Due to this static nature, operator workloads increase because unrelated information must be screened out and numerous displays must be checked to obtain the plant status. Generally, excessive workloads should be reduced because they can lead to human errors that may adversely affect nuclear power plant safety. This paper presents a framework for an operator support system that can substitute the initial responses of the EOPs, or in other words the immediate actions and diagnostic procedures, in the early stages of an emergency. The system assists operators in emergency operations as follows: performing the monitoring tasks in parallel, identifying current risk and latent risk causality, diagnosing the accident, and displaying all information intuitively with a master logic diagram. The risk causalities are analyzed with a functional modeling methodology called multilevel flow modeling. This system is expected to reduce workloads and the time for performing initial emergency response procedures.

참고문헌 (25)

  1. W. Jung, "Analysis of an operators' performance time and its application to a human reliability analysis in nuclear power plants", IEEE Trans. Nucl. Sci, 54(5), pp.1801~1811 (2007)
  2. J. Ahn, "Reflections on the Fukushima Daiichi Nuclear Accident: toward Social-Scientific Literacy and Engineering Resilience" (2015), Springer Nature
  3. J. Park, "An experimental investigation on relationship between PSFs and operator performances in the digital main control room", Ann. Nucl. Energy, 101, pp.58~68 (2017)
  4. J. M. O'Hara, "Advanced control rooms and crew performance issues : implications for human reliability", IEEE Trans. Nucl. Sci, 39(4), pp.919~923 (1992)
  5. SEUNG JUN LEE, "DEVELOPMENT OF AN INTEGRATED DECISION SUPPORT SYSTEM TO AID COGNITIVE ACTIVITIES OF OPERATORS", Nuclear Engineering and Technology, 39(6), pp.703~716 (2007), 한국원자력학회
  6. Y. C. Shin, "Advanced MMIS Design Characteristics of APR1400", ~ (2003)
  7. H. Yoshikawa, "Development of an analysis support system for man-machine system design information", Control Eng. Pract, 5(3), pp.417~425 (1997)
  8. Computer-Based Procedures for Field Workers in Nuclear Power Plants: Development of a Model of Procedure Usage and Identification of Requirements, "J. Oxstrand", Idaho National Laboratory, ~ (2012)
  9. J. -H. Hong, "Computerized procedure system for the APR1400 simulator", Nucl. Eng. Des, 239(12), pp.3092~3104 (2009)[DOI]
  10. J. Ahn, "Deep learning-based procedure compliance check system for nuclear power plant emergency operation", Nucl. Eng. Des, 370, pp.110868~ (2020)
  11. "Operator Support Systems in Nuclear Power Plants", INTERNATIONAL ATOMIC ENERGY AGENCY, ~ (1992)
  12. Development and Review of Plant Specific Emergency Operating Procedures, "I. A. E. Agency", Internat. Atomic Energy Agency, ~ (2006)
  13. Development of Compact Nuclear Simulator, "C. S. Ham", Korea Advanced Energy Research Inst, ~ (1988)
  14. Compact Nuclear Simulator and its Upgrade Plan, "K. -C. Kwon", ~ (1997)
  15. J. C. Park, "Equipment and Performance Upgrade of Compact Nuclear Simulator", ~ (1998)
  16. J. Choi, "A sensor fault-tolerant accident diagnosis system", Sensors, 20(20), pp.5839~ (2020)
  17. H. Wang, "Advanced fault diagnosis method for nuclear power plant based on convolutional gated recurrent network and enhanced particle swarm optimization", Ann. Nucl. Energy, 151, pp.107934~ (2021)
  18. 김재민, "Abnormality diagnosis model for nuclear power plants using two-stage gated recurrent units", Nuclear Engineering and Technology, 52(9), pp.2009~2016 (2020), 한국원자력학회[DOI]
  19. M. Lind, "An introduction to multilevel flow modeling", Int. Electron. J. Nucl. Saf. Simulat, 2(1), pp.22~32 (2011)
  20. On-line Monitoring for Improving Performance of Nuclear Power Plants Part 2: Process and Component Condition Monitoring and Diagnostics, , INTERNATIONAL ATOMIC ENERGY AGENCY, ~ (2008)
  21. Morten Lind, "Functional Modelling for Fault Diagnosis and its Application for NPP", Nuclear Engineering and Technology, 46(6), pp.753~772 (2014), 한국원자력학회
  22. Mengchu Song, "Planning of alternative countermeasures for a station blackout at a boiling water reactor using multilevel fl ow modeling", Nuclear Engineering and Technology, 50(4), pp.542~552 (2018), 한국원자력학회
  23. I. S. Jeon, "Development of an optimal mitigation strategy by estimating the conditional core damage probability with time-dependent recovery actions", Ann. Nucl. Energy, 142, pp.107381~ (2020)
  24. S. J. Lee, "An analytical approach to quantitative effect estimation of operation advisory system based on human cognitive process using the Bayesian belief network", Reliab. Eng. Syst. Saf, 93(4), pp.567~577 (2008)
  25. H. G. Kang, "Information theoretic approach to man-machine interface complexity evaluation", IEEE Trans. Syst. Man Cybern. Syst. Hum, 31(3), pp.163~171 (2001)

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