PWR and BWR Anticipated and Abnormal Plant Transient Research Sponsored by the U.S. Nuclear Regulatory Commission

  • William D. Beckner
  • Fuat Odar
  • L. Harold Sullivan


Increased attention is being given to the analysis of anticipated plant transients and abnormal plant operating conditions. This is in contrast to past regulatory activities devoted primarily to the analysis of design basis accidents (DBA), such as the large-break loss-of-coolant accident (LOCA), which were designed to represent worst or bounding cases. This change has come about due to the realization that anticipated transients with multiple failures (including operator actions) are the major contributors to risk from reactor operations and that the low probability DBAs are relatively small contributors to risk. The accident at Three Mile Island Unit 2 (TMI-2) has shown that anticipated transients, combined with multiple equipment and/or operator failures, can result in significant core damage.


Steam Generator Electric Power Research Institute Pressurize Water Reactor Nuclear Regulatory Commission Boiling Water Reactor 
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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Copyright information

© Springer Science+Business Media New York 1984

Authors and Affiliations

  • William D. Beckner
    • 1
  • Fuat Odar
    • 1
  • L. Harold Sullivan
    • 2
  1. 1.U.S. Nuclear Regulatory CommissionUSA
  2. 2.Los Alamos National LaboratoryLos AlamosUSA

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