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Comparison of Novovoronezh Unit 5 NPP and South Ukraine Unit 1 NPP Level 1 PRA Results

[+] Author Affiliations
Zoran Musicki

Energy & Environmental Sciences, Inc., Stony Brook, NY

Ted Ginsberg

Brookhaven National Laboratory, Upton, NY

Paper No. ICONE10-22601, pp. 397-406; 10 pages
  • 10th International Conference on Nuclear Engineering
  • 10th International Conference on Nuclear Engineering, Volume 2
  • Arlington, Virginia, USA, April 14–18, 2002
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 0-7918-3596-0 | eISBN: 0-7918-3589-8
  • Copyright © 2002 by ASME


This paper describes a study undertaken to explain the risk profile differences in the results of PRAs of two similar VVER-1000 nuclear power plants. The risk profile differences are particularly significant in the area of small steam/feedwater line breaks, small-small LOCAs, support system initiators and containment bypass initiators. A top level (limited depth) approach was used in which we studied design differences, major assumptions, data differences, and also compared the two PRA analyses on an element-by-element basis in order to discern the major causative factors for the risk profile differences. We conclude that the major risk profile differences are due to differences in assumptions and engineering judgment (possibly combined with some design and data differences) involved in treatment of uncertain physical phenomena (primarily sump plugging in LOCAs and turbine building steaming effects in secondary system breaks). Additional major differences are attributable to support system characteristics.

Copyright © 2002 by ASME



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