DOI QR코드

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

  • Kang, Jung Sung (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology) ;
  • Lee, Seung Jun (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology)
  • 투고 : 2021.10.15
  • 심사 : 2022.02.09
  • 발행 : 2022.07.25

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.

키워드

과제정보

This work was supported by a National Research Foundation of Korea (NRF) grant funded by the Korea government (MSIT) (No.NRF-2018M2B2B1065653). This work was also supported by the Nuclear Safety Research Program through the Korea Foundation of Nuclear Safety (KoFONS) using a financial resource granted by the Nuclear Safety and Security Commission (NSSC) of the Republic of Korea (No. 2106007).

참고문헌

  1. W. Jung, J. Park, J. Kim, J. Ha, Analysis of an operators' performance time and its application to a human reliability analysis in nuclear power plants, IEEE Trans. Nucl. Sci. 54 (5) (2007) 1801-1811. https://doi.org/10.1109/TNS.2007.905163
  2. J. Ahn, C. Carson, M. Jensen, K. Juraku, S. Nagasaki, S. Tanaka, Reflections on the Fukushima Daiichi Nuclear Accident: toward Social-Scientific Literacy and Engineering Resilience, Springer Nature, 2015.
  3. J. Park, D. Lee, W. Jung, J. Kim, An experimental investigation on relationship between PSFs and operator performances in the digital main control room, Ann. Nucl. Energy 101 (2017) 58-68. https://doi.org/10.1016/j.anucene.2016.10.020
  4. J.M. O'Hara, R.E. Hall, Advanced control rooms and crew performance issues: implications for human reliability, IEEE Trans. Nucl. Sci. 39 (4) (1992) 919-923. https://doi.org/10.1109/23.159733
  5. S.J. Lee, P.H. Seong, Development of an integrated decision support system to aid cognitive activities of operators, Nucl. Eng. Technol. 39 (6) (2007) 703. https://doi.org/10.5516/NET.2007.39.6.703
  6. Y.C. Shin, H.Y. Chung, T.Y. Song, Advanced MMIS Design Characteristics of APR1400, 2003.
  7. H. Yoshikawa, T. Nakagawa, Y. Nakatani, T. Furuta, A. Hasegawa, Development of an analysis support system for man-machine system design information, Control Eng. Pract. 5 (3) (1997) 417-425. https://doi.org/10.1016/S0967-0661(97)00019-1
  8. J. Oxstrand, K. Le Blanc, Computer-Based Procedures for Field Workers in Nuclear Power Plants: Development of a Model of Procedure Usage and Identification of Requirements, Idaho National Laboratory External Report, 2012.
  9. J.-H. Hong, M.-S. Lee, D.-H. Hwang, Computerized procedure system for the APR1400 simulator, Nucl. Eng. Des. 239 (12) (2009) 3092-3104, https://doi.org/10.1016/j.nucengdes.2009.09.024.
  10. J. Ahn, S.J. Lee, Deep learning-based procedure compliance check system for nuclear power plant emergency operation, Nucl. Eng. Des. 370 (2020) 110868. https://doi.org/10.1016/j.nucengdes.2020.110868
  11. Operator Support Systems in Nuclear Power Plants, INTERNATIONAL ATOMIC ENERGY AGENCY, Vienna, 1992.
  12. I.A.E. Agency, Development and Review of Plant Specific Emergency Operating Procedures, Internat. Atomic Energy Agency, 2006.
  13. C.S. Ham, et al., Development of Compact Nuclear Simulator, Korea Advanced Energy Research Inst., 1988.
  14. K.-C. Kwon, J.-C. Park, C.-H. Jung, J.-S. Lee, J.-Y. Kim, Compact Nuclear Simulator and its Upgrade Plan, 1997.
  15. J.C. Park, et al., Equipment and Performance Upgrade of Compact Nuclear Simulator, 1998.
  16. J. Choi, S.J. Lee, A sensor fault-tolerant accident diagnosis system, Sensors 20 (20) (2020) 5839. https://doi.org/10.3390/s20205839
  17. H. Wang, M.-j. Peng, A. Ayodeji, H. Xia, X.-k. Wang, Z.-k. Li, Advanced fault diagnosis method for nuclear power plant based on convolutional gated recurrent network and enhanced particle swarm optimization, Ann. Nucl. Energy 151 (2021) 107934. https://doi.org/10.1016/j.anucene.2020.107934
  18. J.M. Kim, G. Lee, C. Lee, S.J. Lee, Abnormality diagnosis model for nuclear power plants using two-stage gated recurrent units, Nucl. Eng. Technol. 52 (9) (2020) 2009-2016. https://doi.org/10.1016/j.net.2020.02.002
  19. M. Lind, An introduction to multilevel flow modeling, Int. Electron. J. Nucl. Saf. Simulat. 2 (1) (2011) 22-32.
  20. On-line Monitoring for Improving Performance of Nuclear Power Plants Part 2: Process and Component Condition Monitoring and Diagnostics, INTERNATIONAL ATOMIC ENERGY AGENCY, Vienna, 2008.
  21. M. Lind, X. Zhang, Functional modelling for fault diagnosis and its application for NPP, Nucl. Eng. Technol. 46 (6) (2014) 753-772. https://doi.org/10.5516/NET.04.2014.721
  22. M. Song, A. Gofuku, Planning of alternative countermeasures for a station blackout at a boiling water reactor using multilevel flow modeling, Nucl. Eng. Technol. 50 (4) (2018) 542-552. https://doi.org/10.1016/j.net.2018.03.004
  23. I.S. Jeon, H.G. Kang, Development of an optimal mitigation strategy by estimating the conditional core damage probability with time-dependent recovery actions, Ann. Nucl. Energy 142 (2020) 107381. https://doi.org/10.1016/j.anucene.2020.107381
  24. S.J. Lee, M.C. Kim, P.H. Seong, 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) (2008) 567-577. https://doi.org/10.1016/j.ress.2007.02.004
  25. H.G. Kang, P.H. Seong, Information theoretic approach to man-machine interface complexity evaluation, IEEE Trans. Syst. Man Cybern. Syst. Hum. 31 (3) (2001) 163-171. https://doi.org/10.1109/3468.925655