COBRA-TF Analysis of the High Flux Reactor Hot Channel for a Postulated Large-Break Loss of Coolant Accident

摘要

The High Flux Reactor (HFR) is a researchrnreactor cooled and moderated by light water. It isrna 0.0 MWt tank-in-pool materials testingrnreactor which uses highly enriched plate typernfuel elements in rectangular duct channels thatrncontain small hydraulic diameters for the fuelrndesign. A forced flow circulation system existsrnto provide cooling for the reactor under normalrnoperation. This study includes a simulation of thernHFR core for a postulated large break loss ofrncoolant accident for the reactor using thernCOBRA-TF computer code. During the LOCArnthe heat transfer in the core is changed fromrnforced to natural circulation. For this transient,rnthe concern is that the plate type fuel can exceedrncritical heat flux. COBRA-TF has been chosenrnfor this analysis since it has suitable andrnvalidated two-phase flow models and criticalrnheat flux (CHF) correlations for naturalrncirculation in channels having small hydraulicrndiameters.