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Analyses of Spatial CHF/Rewet Behaviour of Fuel Rod Bundle in Pump-Trip Simulation Experiment With Three-Dimensional Multi-Fluid Porous Media Approach

[+] Author Affiliations
Zoran V. Stosic

Framatome ANP GmbH, Erlangen, Germany

Vladimir D. Stevanovic

University of Belgrade, Belgrade, Yugoslavia

Tadashi Iguchi

Japan Atomic Energy Research Institute, Tokai, Ibaraki, Japan

Paper No. FEDSM2002-31228, pp. 447-457; 11 pages
  • ASME 2002 Joint U.S.-European Fluids Engineering Division Conference
  • Volume 2: Symposia and General Papers, Parts A and B
  • Montreal, Quebec, Canada, July 14–18, 2002
  • Conference Sponsors: Fluids Engineering Division
  • ISBN: 0-7918-3616-9 | eISBN: 0-7918-3600-2
  • Copyright © 2002 by ASME


The investigation of three-dimensional transient propagations of dry-out fronts within a nuclear fuel rod bundle is performed, based on experimental and numerical simulations. The spreading of critical heat flux (CHF) fronts across a bundle, caused by gradual decrease of coolant mass flow rate without power increase is predicted, and the locus of dry patches is shown. Obtained results show that a simultaneous occurrence of CHF and rewet multi-fronts in simulated reactor coolant flow transient are less pronounced than in power transients. Due to a possible building of a vapour zone, the CHF front spatial propagation has to be carefully analysed in transient conditions.

Copyright © 2002 by ASME



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