An Approach to Estimate SBO Risks in Multi-unit Nuclear Power Plants with a Shared Alternate AC Power Source

  • Woo Sik Jung
  • Joon-Eon Yang
  • Jaejoo Ha
Conference paper


An appropriate method to evaluate accurately the amounts of risks, core damage frequencies and site risks, resulting from a station blackout (SBO) event of a multi-unit site that has a shared alternate AC (AAC) power source has been developed. It accommodates the complex inter-unit behaviour of the shared AAC power source under a multi-unit loss of offsite power (LOOP) conditions.


Power Source Nuclear Power Plant Fault Tree Nuclear Regulatory Commission 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.


Unable to display preview. Download preview PDF.

Unable to display preview. Download preview PDF.


  1. 1.
    Mays SE, Krantz EA, Brinsfield W. Multi-unit IPE and PRA issues. Proceedings of the International Topical Meeting on Probability, Reliability, and Safety Assessment PSA ′89, Pittsburgh, Pennsylvania, 1989. p.29-37.Google Scholar
  2. 2.
    Brinsfield W, McClymont A, Krantz EA, Trainer J, Klopp G. Approach to the Evaluation of Multi-Unit Loss of Offsite Power Events. Proceedings of the International Topical Meeting on Probability, Reliability, and Safety Assessment PSA’ 89, Pittsburgh, Pennsylvania, 1989. p.796-800.Google Scholar
  3. 3.
    Kim MK. Risk Analysis of NPP in Multi-Unit Site for Configuration of AAC Power Source. Proceedings of the 5th International Conference on Probabilistic Safety Assessment and Management, Osaka, Japan, 2000.Google Scholar
  4. 4.
    Jung WS, Yang JE, and Ha JJ, “A new method to evaluate alternate AC power source effects in multi-unit nuclear power plants,” Reliability Engineering and System Safety, 82, pp. 165–172, 2003.CrossRefGoogle Scholar
  5. 5.
    Korea Electric Power Corporation. Ulchin Units 3 & 4 Final Probabilistic Safety Assessment Report, 1997.Google Scholar
  6. 6.
    U.S. Nuclear Regulatory Commission. Common-Cause Failure Parameter Estimations. NUREG/CR-5497, INEL/EXT-97-01328, 1998.Google Scholar

Copyright information

© Springer-Verlag London 2004

Authors and Affiliations

  • Woo Sik Jung
    • 1
  • Joon-Eon Yang
    • 1
  • Jaejoo Ha
    • 1
  1. 1.Korea Atomic Energy Research InstituteYusong, DaejonKorea

Personalised recommendations