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 sudden decrease of coolant mass flow rate followed by delayed gradual decrease of power generation is predicted, and the locus of dry patches is shown. Simultaneous occurrence of CHF and rewet multi-fronts in here-analysed flow transient has not been detected so obvious as in power transient, previously analysed. Due to a possible building of a vapour zone, the CHF front spatial propagation has to be carefully analysed in transient conditions.

Volume Subject Area:
Thermal Hydraulics
Topics:
Critical heat flux, Flow (Dynamics), Fluids, Fuel rods, Numerical analysis, Porous materials, Simulation, Transients (Dynamics), Computer simulation, Coolants, Energy generation
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Copyright © 2002
 by ASME
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