Advertisement

INDESCO: Integrated Decision Support System to Aid the Cognitive Activities of Operators

  • Seung Jun Lee
  • Man Cheol Kim
  • Poong Hyun Seong
Chapter
  • 1.1k Downloads
Part of the Springer Series in Reliability Engineering book series (RELIABILITY)

Abstract

The possibility of human failure or human error has a significant impact on the safety or reliability of large-scale systems. Most analysis results of accidents, including Chernobyl and TMI-2 accidents indicate that human error is one of the main causes of accidents. Forty-eight percent of incidents in an analysis of 180 significant NPP events occurring in the United States were attributed to failures in human factors [1]. Human factors are analyzed to prevent human errors and are considered in performing a more reliable safety assessment of a system. HRA and human factors are described in Chapter 7 and Chapter 8. An approach to assessing the safety of a system, including human operators, is introduced in Chapter 11, which suggests an integrated safety model that includes both digital control systems and human operators. The adequacy of procedures, stress (available time), training/experience of human operators, and sensor failure probabilities are found to be relatively important compared to other factors in a sensitivity analysis described in Section 11.3.5. The safety of a system is more affected by these four factors. Efficient improvement in the safety of a system is achieved by improving them in the system. Such factors related to humans have been becoming more important than other factors related to hardware and software because only highly reliable hardware and software components can be used in safety-critical systems, such as NPPs.

Keywords

Nuclear Power Plant Failure Probability Steam Generator Commission Error Korea Atomic Energy Research Institute 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

Preview

Unable to display preview. Download preview PDF.

Unable to display preview. Download preview PDF.

References

  1. [1]
    Marsden P (1996) Procedures in the nuclear industry, In Stanton, N. (ed.). Human Factors in Nuclear Safety:99–116Google Scholar
  2. [2]
    Miller CA, Funk HB, Goldman RP, Meisner J, Wu P (2005) Implications of adaptive vs. adaptable UIs on decision making. Human Computer Interaction International 2005Google Scholar
  3. [3]
    Miller CA (2005) Trust in adaptive automation: The role of etiquette in tuning trust via analogical and affective methods. Human Computer Interaction International 2005Google Scholar
  4. [4]
    Inagaki T, Furukawa H, Itoh M (2005) Human interaction with adaptive automaton: Strategies for trading of control under possibility of over-trust and complacency. Human Computer Interaction International 2005Google Scholar
  5. [5]
    Kawai K, Takizawa Y, Watanabe S (1999) Advanced automation for powergeneration plants-past, present and future. Control Engineering Practice 7:1405–1411CrossRefGoogle Scholar
  6. [6]
    Wickens CD (2000) Engineering psychology and human performance. New York: Harper CollinsGoogle Scholar
  7. [7]
    Perrow C (1984) Normal accidents. New York: Basic BooksGoogle Scholar
  8. [8]
    Green M (1999) Human machine interaction research at the OECD Halden reactor project. People in Control: An International Conference on Human Interfaces in Control Rooms, Cockpits and Command Centres:463Google Scholar
  9. [9]
    Lee SJ, Seong PH (2007) Development of an integrated decision support system to aid cognitive activities of operators. Nuclear Engineering and TechnologyGoogle Scholar
  10. [10]
    Ohi T, Yoshikawa H, Kitamura M, Furuta K, Gofuku A, Itoh K, Wei W, Ozaki Y (2002) Development of an advanced human-machine interface system to enhanced operating availability of nuclear power plants. International Symposium on the Future I&C for NPP (ISOFIC2002). Seoul:297-300Google Scholar
  11. [11]
    Chang SH, Choi SS, Park JK, Heo G, Kim HG (1999) Development of an advanced human-machine interface for next generation nuclear power plants. Reliability Engineering and System Safety 64:109-126CrossRefGoogle Scholar
  12. [12]
    Kim IS (1994) Computerized systems for on-line management of failures: a state-ofthe-art discussion of alarm systems and diagnostic systems applied in the nuclear industry. Reliability Engineering and Safety System 44:279–295CrossRefGoogle Scholar
  13. [13]
    Ruan D, Fantoni PF, et al. (2002) Power surveillance and diagnostics: SpringerGoogle Scholar
  14. [14]
    Gofuku A, Ozaki Y, Ito K (2004) A dynamic operation permission system for pressurized water reactor plants. International Symposium on the Future I&C for NPP (ISOFIC2004). Kyoto:360–365Google Scholar
  15. [15]
    Kim JH, Seong PH (2007) The effect of information types on diagnostic strategies in the information aid. Reliability Engineering and System Safety. 92:171-186CrossRefGoogle Scholar
  16. [16]
    Barriere M, Bley D, Cooper S, Forester J, Kolaczkowski A, Luckas W, Parry G, Ramey-Smith A, Thompson C, Whitehead D, Wreathall J (2000) 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.Google Scholar
  17. [17]
    Thompson CM, Cooper SE, Bley DC, Forester JA, Wreathall J (1997) The application of ATHEANA: a technique for human error analysis. IEEE Sixth Annual Human Factors MeetingGoogle Scholar
  18. [18]
    Kim MC, Seong PH (2004) A quantitative model of system-man interaction based on discrete function theory. Journal of the Korean Nuclear Society 36:430–450Google Scholar
  19. [19]
    Niwa Y, Yoshikawa H (2003) The adaptation to main control room of a new human machine interface design. Human Computer Interaction International 2003:1406-1410Google Scholar
  20. [20]
    Lee SJ, Kim MC, Seong PH (2007) An analytical approach to quantitative effect estimation of operation advisory system based on human cognitive process using the Bayesian belief network. Reliability Engineering and System SafetyGoogle Scholar
  21. [21]
    Kim JT, Kwon KC, Hwang IK, Lee DY, Park WM, Kim JS, Lee SJ (2001) Development of advanced I&C in nuclear power plants: ADIOS and ASICS. Nuclear Engineering and Design 207:105–119CrossRefGoogle Scholar
  22. [22]
    Lee SJ, Seong PH (2005) A dynamic neural network based accident diagnosis advisory system for nuclear power plants. Progress in Nuclear Energy 46:268–281CrossRefGoogle Scholar
  23. [23]
    Varde PV, Sankar S, Verma AK (1997) An operator support system for research reactor operations and fault diagnosis through a connectionist framework and PSA based knowledge based systems. Reliability Engineering and System Safety 60:53–69CrossRefGoogle Scholar
  24. [24]
    Yangping Z, Bingquan Z, DongXin W (2000) Application of genetic algorithms to fault diagnosis in nuclear power plants. Reliability Engineering and System Safety 67:153–160CrossRefGoogle Scholar
  25. [25]
    Mo K, Lee SJ, Seong PH (2007) A dynamic neural network aggregation model for transient diagnosis in nuclear power plants. Progress in Nuclear Energy 49-3:262–272CrossRefGoogle Scholar
  26. [26]
    Pirus D, Chambon Y (1997) The computerized procedures for the French N4 series. IEEE Transaction on Nuclear Science 8-13:6/3–6/9Google Scholar
  27. [27]
    Converse SA, Perez P, Clay M, Meyer S (1992) Computerized procedures for nuclear power plants: evaluation of the computerized procedures manual (COPMA-II). IEEE Transactions on Nuclear Science 7-11:167–172Google Scholar
  28. [28]
    Mo K, Lee SJ, Seong PH (2007) A neural network based operation guidance system for procedure presentation and operation validation in nuclear power plants. Annals of Nuclear Energy 34-10:813–823CrossRefGoogle Scholar
  29. [29]
    Jensen F (1994) Implementation aspects of various propagation algorithms in Hugin. Research Report R-94-2014, Department of Mathematics and Computer Science, Aalborg University, DenmarkGoogle Scholar
  30. [30]
    Jensen F., Andersen SK (1990) Approximations in Bayesian belief universes for knowledge-based systems. In Proceedings of the Sixth Conference on Uncertainty in Artificial Intelligence. Cambridge, Massachusetts:162–169Google Scholar
  31. [31]
    Swain AD, Guttmann HE (1983) Handbook of human reliability analysis with emphasis on nuclear power plant applications, NUREG-1278. U.S. Nuclear Regulatory Commission: Washington D.C.Google Scholar
  32. [32]
    Advanced compact nuclear simulator textbook. Nuclear Training Center in Korea Atomic Energy Research Institute (1990)Google Scholar

Copyright information

© Springer London 2009

Authors and Affiliations

  • Seung Jun Lee
    • 1
  • Man Cheol Kim
    • 1
  • Poong Hyun Seong
    • 2
  1. 1.Integrated Safety Assessment DivisionKorea Atomic Energy Research InstituteDaejeonKorea, Republic of
  2. 2.Department of Nuclear and Quantum EngineeringKorea Advanced Institute of Science and TechnologyDaejeonKorea, Republic of

Personalised recommendations