Issues in System Reliability and Risk Model

  • Hyun Gook Kang
Part of the Springer Series in Reliability Engineering book series (RELIABILITY)


The application of large-scale digital or computer systems involves many components, elements, and modules. System reliability and safety need to be calculated no matter how complicated is the structure. Estimation of system reliability/safety provides useful information for system design and verification. Risk allocation to the designed system in a balanced manner is an application example.


Failure Probability System Reliability Digital System Fault Tree Bayesian Belief Network 
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.


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  1. [1]
    Kang HG, Jang SC, Ha JJ (2002) Evaluation of the impact of the digital safety-critical I&C systems, ISOFIC2002, Seoul, Korea, November 2002Google Scholar
  2. [2]
    Sancaktar S, Schulz T (2003) Development of the PRA for the AP1000, ICAPP '03, Cordoba, Spain, May 2003Google Scholar
  3. [3]
    Hisamochi K, Suzuki H, Oda S (2002) Importance evaluation for digital control systems of ABWR Plant, The 7th Korea-Japan PSA Workshop, Jeju, Korea, May 2002Google Scholar
  4. [4]
    HSE (1998) The use of computers in safety-critical applications, London, HSE booksGoogle Scholar
  5. [5]
    Kang HG, et al. (2003) Survey of the advanced designs of safety-critical digital systems from the PSA viewpoint, Korea Atomic Energy Research Institute, KAERI/AR-00669/2003Google Scholar
  6. [6]
    Goldberg BE, Everhart K, Stevens R, Babbitt N III, Clemens P, Stout L (1994) System engineering “Toolbox” for design-oriented engineers, NASA Reference Publication 1358Google Scholar
  7. [7]
    Meshkat L, Dugan JB, Andrews JD (2000) Analysis of safety systems with ondemand and dynamic failure modes, Proceedings of 2000 RMGoogle Scholar
  8. [8]
    White RM, Boettcher DB (1994) Putting Sizewell B digital protection in context, Nuclear Engineering International, pp. 41–43Google Scholar
  9. [9]
    Parnas DL, Asmis GJK, Madey J (1991) Assessment of safety-critical software in nuclear power plants, Nuclear Safety, Vol. 32, No. 2Google Scholar
  10. [10]
    Butler RW, Finelli GB (1993) The infeasibility of quantifying the reliability of lifecritical real-time software, IEEE Transactions on Software Engineering, Vol. 19, No. 1Google Scholar
  11. [11]
    Kang HG, Sung T, et al (2000) Determination of the Number of Software Tests Using Probabilistic Safety Assessment KNS conference, Proceeding of Korean Nuclear Society, Taejon, KoreaGoogle Scholar
  12. [12]
    Littlewood B, Wright D (1997) Some conservative stopping rules for the operational testing of safety-critical software, IEEE Trans. Software Engineering, Vol. 23, No. 11, pp. 673–685CrossRefGoogle Scholar
  13. [13]
    Saiedian H (1996) An Invitation to formal methods, ComputerGoogle Scholar
  14. [14]
    Rushby J (1993) Formal methods and the certification of critical systems, SRI-CSL-93-07, Computer Science Laboratory, SRI International, Menlo ParkGoogle Scholar
  15. [15]
    Welbourne D (1997) Safety critical software in nuclear power, The GEC Journal of Technology, Vol. 14, No. 1Google Scholar
  16. [16]
    Dahll G (1998) The use of Bayesian belief nets in safety assessment of software based system, HWP-527, Halden ProjectGoogle Scholar
  17. [17]
    Eom HS, et al. (2001) Survey of Bayesian belief nets for quantitative reliability assessment of safety critical software used in nuclear power plants, Korea Atomic Energy Research Institute, KAERI/AR-594-2001, 2001Google Scholar
  18. [18]
    Littlewood B, Popov P, Strigini L (1999) A note on estimation of functionally diverse system, Reliability Engineering and System Safety, Vol. 66, No. 1, pp. 93-95CrossRefGoogle Scholar
  19. [19]
    Bastl W, Bock HW (1998) German qualification and assessment of digital I&C systems important to safety, Reliability Engineering and System Safety, Vol. 59, pp. 163-170CrossRefGoogle Scholar
  20. [20]
    Choi JG, Seong PH (2001) Dependability estimation of a digital system with consideration of software masking effects on hardware faults, Reliability Engineering and System Safety, Vol. 71, pp. 45-55CrossRefGoogle Scholar
  21. [21]
    Bayrak T, Grabowski MR (2002) Safety-critical wide area network performance evaluation, ECIS 2002, June 6–8, Gdańsk, PolandGoogle Scholar
  22. [22]
    Kang HG, Jang SC (2006) Application of condition-based HRA method for a manual actuation of the safety features in a nuclear power plant, Reliability Engineering & System Safety, Vol. 91Google Scholar
  23. [23]
    Kauffmann JV, Lanik GT, Spence RA, Trager EA (1992) Operating experience feedback report – human performance in operating events, USNRC, NUREG-1257, Vol. 8, Washington DCGoogle Scholar
  24. [24]
    Decortis F (1993) Operator strategies in a dynamic environment in relation to an operator model, Ergonomics, Vol. 36, No. 11Google Scholar
  25. [25]
    Park J, Jung W (2003) The requisite characteristics for diagnosis procedures based on the empirical findings of the operators’ behavior under emergency situations, Reliability Engineering & System Safety, Volume 81, Issue 2Google Scholar
  26. [26]
    Julius JA, Jorgenson EJ, Parry GW, Mosleh AM (1996) Procedure for the analysis of errors of commission during non-power mode of nuclear power plant operation, Reliability Engineering & System Safety, Vol. 53Google Scholar
  27. [27]
    OECD/NEA Committee on the safety of nuclear installations, 1999, ICDE project report on collection and analysis of common-cause failures of centrifugal pumps, NEA/CSNI/R(99)2Google Scholar
  28. [28]
    OECD/NEA Committee on the safety of nuclear installations, 2003, ICDE project report: Collection and analysis of common-cause failures of check valves, NEA/CSNI/R(2003)15Google Scholar

Copyright information

© Springer London 2009

Authors and Affiliations

  • Hyun Gook Kang
    • 1
  1. 1.Integrated Safety Assessment DivisionKorea Atomic Energy Research InstituteDaejeonKorea, Republic of

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