The US NRC Advanced Gas Reactor Evaluator (AGREE)
NURETH-14 - 2011 September 25-30

Presented at:
2011 September 25-30
Toronto, Canada
Session Title:
G4-2 - Gas Cooled Fast Reactors and Very High Temperature Reactors; System Calculations

Timothy Drzewiecki (University of Michigan)
Volkan Seker (University of Michigan)
Joseph Kelly (US NRC)
Thomas Downar (University of Michigan)


A Prismatic Module Reactor (PMR) core fluids model has been developed in support of the US NRC Next Generation Nuclear Plant (NGNP) evaluation model.  The PMR core fluids modeling relies on a subchannel approach in which the primary coolant flowpath through the core region and vertical in-core and ex-core gaps can be modeled as individual subchannels.  These subchannels are connected together to represent a three dimensional reactor.   An initial validation calculation has been performed using data available in literature for bypass flow.  The predicted bypass flow was within 2.6% of the value reported in the literature.   Further verification and validation is awaiting the completion of the coupling of the fluids model with a triangular solid heat conduction model. 

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