Fusion Science and Technology / Volume 61 / Number 1T / January 2012 / Pages 161-166
Fission / Proceedings of the Fifteenth International Conference on Emerging Nuclear Energy Systems
This paper presents the results of a coupled 3-D thermal-hydraulics and CFD analysis of helium flow in a coolant channel of a prismatic core, Very High Temperature Reactor (VHTR). Results are used to develop a turbulent convection heat transfer correlation that accounts for induced mixing in the entrance region as:
h = [0.10(k/D)Reb0.653Prb0.4][1 + 0.57e-(0.20z/D)]
The entrance effect (second term) increases the local turbulent heat transfer coefficient, but diminishes for z/D > 25. This correlation is within ± 2% of the numerical results.