Conference Proceedings Paper
Influence of Numerical Tools on the Flow and Heat Transfer of Super-Critical Water
NURETH-14 - 2011 September 25-30
A. Shams (Nuclear Research and Consultancy Group, Petten)
D.C. Visser (Nuclear Research and Consultancy Group, Petten)
F. Roelofs (Nuclear Research and Consultancy Group, Petten)
In a Supercritical Water Reactor (SCWR) the reactor core is cooled with supercritical water
(SCW). For the design and operation of a SCWR, the characteristics of the heat transfer from the
fuel rods to the SCW coolant needs to be well understood. These heat transfer characteristics are
complex and cannot be captured by the correlations that are currently available in literature.
Predicting the heat transfer to SCW has also become a challenge for Computational Fluid
Dynamics (CFD) models. In the present study, the influence of numerical tools on the
supercritical water flowing through a heated tube configuration has been investigated in
preparation for analyses of a rod bundle validation case. A wide range of 2D axi-symmetrical and
full 3D calculations are performed and compared for the SCW tube experiments of Yamagata and
Ornatskiy. In addition, different meshing techniques, i.e. hybrid (hexa- and polyhedral), were
used to achieve an optimal mesh resolution for such high Prandtl number flows. Furthermore, the
influence of the applied meshing strategy in the transition from near wall to bulk region has been
investigated for the prediction of the overall flow topology and heat transfer.
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