@inproceedings{0dff646313be42aebdc9a2a081ed8f62,
title = "Steady-state, whole-core prismatic VHTR simulation including core bypass",
abstract = "The neutron transport code DeCART and the commercial CFD code STAR-CD are being integrated into the SHARP reactor analysis toolkit to enable the extension of it's capabilities to high-fidelity analysis of prismatic VHTR cores. The studies described herein provide a preliminary evaluation of the applicability of RANS-based CFD methods to the prediction of fluid flow and heat transfer within a large symmetric region of a VHTR core. Simulations considering a single flow channel define mesh density requirements and quantify impacts of detailed geometric details on turbulent flow development. Simulations of a single column of blocks identify the need for detailed power distributions and for including the bypass flow between columns of blocks in full core simulations. While additional development of the meshing strategy and tools is needed, a coarse mesh simulation of a 116th segment of a VHTR core with bypass flow provides a preliminary demonstration of applicability.",
author = "Pointer, {W. D.} and Thomas, {J. W.}",
year = "2010",
language = "English",
isbn = "9781617386435",
series = "International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010",
pages = "317--326",
booktitle = "International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010",
note = "International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010 ; Conference date: 13-06-2010 Through 17-06-2010",
}