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Numerical Simulation of Reflooding Behavior in Tight-Lattice Rod Bundles

Yoshio Murao, Tsuneyuki Hojo

Nuclear Technology / Volume 80 / Number 1 / January 1988 / Pages 83-92

Technical Paper / Advanced Light Water Reactor / Fission Reactor / dx.doi.org/10.13182/NT88-A35551

To evaluate the applicability of the reflood analysis code REFLA for ordinal pressurized water reactors to the analysis of reflooding phenomena in light water high conversion reactors (LWHCRs) with tight-lattice cores, a numerical simulation of the NEPTUN LWHCR test was performed with the REFLA code. The NEPTUN LWHCR test was performed at the Swiss Federal Institute for Reactor Research with a test section simulating the tight-lattice core of an LWHCR. The results indicate no potential problems in the use of REFLA for the simulation of reflooding behavior in tight-lattice rod bundles. To improve the code, however, it is recommended to modify models of core heat transfer at a high flooding rate and core water distribution (integration of droplet flow) in the axial direction, and to investigate core pressure drop and horizontal cross flow.