Conference Proceedings Paper
MODELING APPROACH FOR ANNULAR FUEL ELEMENTS USING THE ASSERT-PV SUBCHANNEL CODE
CNS 24th Nuclear Simulation Symposium - 2012 October 15-16
Armando Nava Dominguez (Atomic Energy of Canada Limited)
Yanfei Rao (Atomic Energy of Canada Limited)
The internally and externally cooled annular fuel (hereafter called annular fuel) is under consideration for a new high burn-up fuel bundle design in Atomic Energy of Canada Limited (AECL) for its current, and its Generation IV reactor.
An assessment of different options to model a bundle fuelled with annular fuel elements is presented. Two options are discussed: 1) Modify the subchannel code ASSERT-PV to handle multiple types of elements in the same bundle, and 2) coupling ASSERT-PV with an external application. Based on this assessment, the selected option is to couple ASSERT-PV with the thermalhydraulic system code CATHENA.
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