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Preliminary Analysis of Influence of Uncertainty Parameters for CAP1400 LBLOCA Accident

[+] Author Affiliations
Zhanfei Qi, Lu Lu, Weiwei Wang

Shanghai Nuclear Engineering Research and Design Institute, Shanghai, China

Paper No. ICONE25-66723, pp. V006T08A053; 5 pages
doi:10.1115/ICONE25-66723
From:
  • 2017 25th International Conference on Nuclear Engineering
  • Volume 6: Thermal-Hydraulics
  • Shanghai, China, July 2–6, 2017
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5784-7
  • Copyright © 2017 by ASME

abstract

The best-estimated methodology is applied for CAP1400 LBLOCA. Based on the sampling and calculation results, the influence of uncertainty parameters including plant initial conditions parameters, core power distribution parameters, global system thermal-hydraulic parameters and local hot rod parameters are evaluated. The major uncertainty parameters are figured out. Moreover, all uncertainty parameters considered in CAP1400 LBLOCA are ranked by their influences. The analysis results show that the break area, relative power of middle third of core, the accumulator initial pressure give the most contribution to PCT of CAP1400 LBLOCA. The uncertainty parameters could be optimized according this paper in the future.

Copyright © 2017 by ASME

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