Skip to main content
SpringerLink
Log in

Design of an Integrated Operator Support System for Advanced NPP MCRs: Issues and Perspectives

  • Chapter
  • First Online:
Progress of Nuclear Safety for Symbiosis and Sustainability

Abstract

Recently, human error has been highlighted as one of the main causes of accidents in nuclear power plants (NPPs). In order to prevent human errors during the main control room (MCR) operations, which are highly complex and mentally taxing activities, improved interfaces and operator support systems have been developed for advanced MCRs. Although operator support systems have the capability to improve the safety and reliability of an NPP, inappropriate designs can have adverse effects on the system safety. Designs based on systematic development frames and validation/verification of the systems are pivotal strategies to circumvent the negative effects of operator support systems. In this paper, an integrated operator support system designed to aid the cognitive activities of operators as well as theoretical and experimental evaluation methods of operator support systems are reviewed. From this review, it was concluded that not only issues about systems (e.g., the accuracy of the system outputs),but also issues about human operators who use the systems (for instance, information quality, the operator’s trust and dependency on support systems) should be considered in the design of efficient operator support systems.

This is a preview of subscription content, log in via an institution to check access.

Access this chapter

Log in via an institution
Chapter
USD 29.95
Price excludes VAT (USA)
  • Available as PDF
  • Read on any device
  • Instant download
  • Own it forever
eBook
USD 84.99
Price excludes VAT (USA)
  • Available as EPUB and PDF
  • Read on any device
  • Instant download
  • Own it forever
Softcover Book
USD 109.99
Price excludes VAT (USA)
  • Compact, lightweight edition
  • Dispatched in 3 to 5 business days
  • Free shipping worldwide - see info
Hardcover Book
USD 109.99
Price excludes VAT (USA)
  • Durable hardcover edition
  • Dispatched in 3 to 5 business days
  • Free shipping worldwide - see info

Tax calculation will be finalised at checkout

Purchases are for personal use only

Institutional subscriptions

References

  1. P. Marsden, Procedures in the nuclear industry, in Human Factors in Nuclear Safety, ed. by N. Stanton (Taylor & Francis, London, 1996)

    Google Scholar 

  2. H. Yoshikawa, T. Nakagawa, Y. Nakatani, T. Furuta, A. Hasegawa, Development of an analysis support system for man–machine system design information. Contr. Eng. Pract. 5, 417 (1997)

    Article  Google Scholar 

  3. I.S. Kim, Computerized systems for on-line management of failures: a state-of-the-art discussion of alarm systems and diagnostic systems applied in the nuclear industry. Reliab. Eng. Saf. Syst. 44, 279 (1994)

    Article  Google Scholar 

  4. M.S. Lee, J.H. Hong, J.K. Suh, S.H. Lee, D.H. Hwang, Development of human factors validation system for the advanced control room of APR1400. J. Nucl. Sci. Technol. 46(1), 90–101 (2009)

    Article  Google Scholar 

  5. S.J. Lee, P.H. Seong, Development of an integrated decision support system to aid cognitive process of operators. Nucl. Eng. Technol. 39(6), 703–717 (2007)

    Article  Google Scholar 

  6. S.J. Lee, M.C. Kim, P.H. Seong, An analytic 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), 567–577 (2008)

    Article  Google Scholar 

  7. S.J. Lee, P.H. Seong, Experimental investigation into the effects of decision support systems on operator performance. J. Nucl. Sci. Technol. 46(12), 1178–1187 (2009)

    Article  Google Scholar 

  8. D. Ruan, P.F. Fantoni, Power Plant Surveillance and Diagnostics (Springer, Berlin, 2002)

    Book  Google Scholar 

  9. A. Gofuku, Y. Ozaki, K. Ito, A dynamic operation permission system for pressurized water reactor plants, in Proceedings of the International Symposium on the Future I&C for NPP (ISOFIC2004), Kyoto, Japan, 2004

    Google Scholar 

  10. J.H. Kim, P.H. Seong, The types on effect of information diagnostic strategies in the information aid. Reliab. Eng. Syst. Saf. 92, 171 (2007)

    Article  Google Scholar 

  11. H. Yoshikawa, Human-machine interaction in nuclear power plants. Nucl. Eng. Technol. 79(2), 151–158 (2005)

    Google Scholar 

  12. C.D. Wickens, Engineering Psychology and Human Performance (Harper Collins, New York, 2000)

    Google Scholar 

  13. C. Perrow, Normal Accidents (Basic Books, New York, 1984)

    Google Scholar 

  14. M. Green, Human machine interaction research at the OECD Halden reactor project, in People in Control: An International Conference on Human Interfaces in Control Rooms, Cockpits and Command Centres, 1999

    Google Scholar 

  15. C.A. Miller, H.B. Funk, R.P. Goldman, J. Meisner, P. Wu, Implications of adaptive vs. adaptable UIs on decision making. Human computer interaction international 2005, Las Vegas, U.S.A, 6–8 July 2005

    Google Scholar 

  16. M. Barriere, D. Bley, S. Cooper, J. Forester, A. Kolaczkowski, W. Luckas, G. Parry, A. Ramey-Smith, C. Thompson, D. Whitehead, J. Wreathalll, Technical basis and implementation guideline for a technique for human event analysis (ATHEANA), NUREG-1624, Rev. 1, U.S. Nuclear Regulatory Commission, Washington D.C, 2000

    Google Scholar 

  17. C.M. Thompson, S.E. Cooper, D.C. Bley, J.A. Forester, J. Wreathall, The application of ATHEANA: A technique for human error analysis, IEEE Sixth Annual Human Factors Meeting, 1997

    Google Scholar 

  18. M.C. Kim, P.H. Seong, a quantitative model of system-man interaction based on discrete function theory. J. Korean Nucl. Soc. 36, 430 (2004)

    Google Scholar 

  19. J.T. Kim, K.C. Kwon, I.K. Hwang, D.Y. Lee, W.M. Park, J.S. Kim, S.J. Lee, Development of advanced I&C in nuclear power plants: ADIOS and ASICS. Nucl. Eng. Des. 207, 105 (2001)

    Article  Google Scholar 

  20. P.V. Varde, S. Sankar, A.K. Verma, An operator support system for research reactor operations and fault diagnosis through a connectionist framework and PSA based knowledge based systems. Reliab. Eng. Syst. Saf. 60, 53 (1997)

    Article  Google Scholar 

  21. S.J. Lee, P.H. Seong, A dynamic neural network based accident diagnosis advisory system for nuclear power plants. Prog. Nucl. Energy 46, 268 (2004)

    Article  Google Scholar 

  22. Y. Zhou, B. Zhao, D. Wu, Application of genetic algorithms to fault diagnosis in nuclear power plants. Reliab. Eng. Syst. Saf. 67, 153 (2000)

    Article  Google Scholar 

  23. D. Pirus, Y. Chambon, The computerized procedures for the French N4 series. IEEE Trans. Nucl. Sci. 8, 639 (1997)

    Google Scholar 

  24. S.A. Converse, P. Perez, M. Clay, S. Meyer, Computerized procedures for nuclear power plants: evaluation of the computerized procedures manual (COPMA-II). IEEE Trans. Nucl. Sci. 7, 167 (1992)

    Google Scholar 

  25. M.C. Kim, P.H. Seong, An analytic model for situation assessment of nuclear power plant operators based on bayesian interface. Reliab. Eng. Syst. Saf. 96, 270–282 (2006)

    Article  Google Scholar 

  26. J. Raaumakers, W. Venduyn, Individual differences and the effects of an information aid in performance of a fault diagnosis task. Ergonomics 39(7), 966–979 (1996)

    Article  Google Scholar 

  27. M.C. Kim, P.H. Seong, A computational method for probabilistic safety assessment of I&C systems and human operators in nuclear power plants. Reliab. Eng. Syst. Saf. 91, 580–593 (2006)

    Article  Google Scholar 

  28. Advanced Compact Nuclear Simulator Textbook, Nuclear Training Center in Korea Atomic Energy Research Institute, 1990

    Google Scholar 

  29. J. Raaumakers, W. Venduyn, Individual differences and the effects of an information aid in performance of a fault diagnosis task. Ergonomics 39, 966–979 (1999)

    Article  Google Scholar 

  30. H. Seok, H.C. No, Development of a software for the micro simulator for Kori nuclear power plant unit 2. Nucl. Technol. 106, 384–396 (1994)

    Google Scholar 

  31. Y.R. Sim, M.C. Na, H.C. No, Development of a small-scale simulator for designing advanced control algorithms at nuclear power, KNS Autumn Meeting, Yongpyung, Korea, 2002

    Google Scholar 

  32. NASA Ames Research Center, NASA Task Load Index (TLX) Version: 2.0 (2010). http://www.nrl.navy.mil/aic/ide/NASATLX.php. Accessed 22 Nov 2010

  33. S.G. Hart, L.E. Straveland, Development of NASA-TLX (task load index): Results of empirical and theoretical research, in Human Mental Workload, ed. by P.A. Hancock, N. Meshkati (North-Holland, Amsterdam, 1998)

    Google Scholar 

  34. J.H. Kim, P.H. Seong, A quantitative approach to modeling the information flow of diagnosis tasks in NPP. Reliab. Eng. Syst. Saf. 80, 81–94 (2003)

    Article  Google Scholar 

Download references

Acknowledgement

This work was supported by Nuclear Research & Development Program of the National Research Foundation of Korea grant, funded by the Korean government, Ministry of Science, ICT & Future Planning.

Author information

Authors and Affiliations

  1. Integrated Safety Assessment Division, Korea Atomic Energy Research Institute, Daedeok-daero 1045, Yuseong-gu, Daejeon, 305-353, Republic of Korea

    Seung Jun Lee

  2. Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 335 Gwahak-ro, Yuseong-gu, Daejeon, 305-701, Republic of Korea

    Poong Hyun Seong

Authors
  1. Seung Jun Lee
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. Poong Hyun Seong
    View author publications

    You can also search for this author in PubMed Google Scholar

Corresponding author

Correspondence to Seung Jun Lee .

Editor information

Editors and Affiliations

  1. Kyoto University, Kyoto, Japan

    Hidekazu Yoshikawa

  2. College of Nuclear Science and Technolog, Harbin Engineering University, Harbin, China

    Zhijian Zhang

Rights and permissions

Reprints and permissions

Copyright information

© 2014 Springer Japan

About this chapter

Cite this chapter

Lee, S.J., Seong, P.H. (2014). Design of an Integrated Operator Support System for Advanced NPP MCRs: Issues and Perspectives. In: Yoshikawa, H., Zhang, Z. (eds) Progress of Nuclear Safety for Symbiosis and Sustainability. Springer, Tokyo. https://doi.org/10.1007/978-4-431-54610-8_2

Download citation

  • DOI: https://doi.org/10.1007/978-4-431-54610-8_2

  • Published:

  • Publisher Name: Springer, Tokyo

  • Print ISBN: 978-4-431-54609-2

  • Online ISBN: 978-4-431-54610-8

  • eBook Packages: EnergyEnergy (R0)

Publish with us

Policies and ethics

Search

Navigation