MODELING APPROACH FOR ANNULAR FUEL ELEMENTS USING THE ASSERT-PV SUBCHANNEL CODE
CNS 24th Nuclear Simulation Symposium - 2012 October 15-16


Presented at:
CNS 24th Nuclear Simulation Symposium
2012 October 15-16
Location:
Ottawa,Canada
Session Title:
Technical 7: Thermalhydraulics & Safety

Authors:
Armando Nava Dominguez (Atomic Energy of Canada Limited)
Yanfei Rao (Atomic Energy of Canada Limited)
  

Abstract

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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