Abstract— Development of quick and versatile simulation packages to investigate time dependent heat transfer phenomena in nuclear reactors or steam generators is an ongoing research interest. The work presented herein is an alternative attempt to address this issue employing a single heated channel framework. A homogenous equivalent mixture is assumed for the two phase flow inside the channel. The sectionalized compressible formalism is further refined and the resultant PDEs are cast into a nodalized layout employing the method of lines as a reduction scheme. Simulation results are presented for the transient heat transfer inside a coolant channel of a nuclear reactor core wherein the incumbent heat flux is affected through an inherent thermo-neutronic feedback mechanism. The overall model reduction strategy likewise provides a suitable platform for the purpose of stability analysis or control synthesis practices.
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