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Effects of Graphite Surface Roughness on Bypass Flow Computations for an HTGR

[+] Author Affiliations
Yu-Hsin Tung

National Tsing Hua University, Hsinchu, Taiwan

Richard W. Johnson

Idaho National Laboratory, Idaho Falls, ID

Hiroyuki Sato

Japan Atomic Energy Agency, Oarai, Ibaraki, Japan

Paper No. PVP2011-58053, pp. 311-320; 10 pages
doi:10.1115/PVP2011-58053
From:
  • ASME 2011 Pressure Vessels and Piping Conference
  • Volume 5: High-Pressure Technology; Nondestructive Evaluation; Nuclear Engineering
  • Baltimore, Maryland, USA, July 17–21, 2011
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 978-0-7918-4455-7
  • Copyright © 2011 by ASME

abstract

Bypass flow in a prismatic high temperature gas reactor (HTGR) occurs between graphite blocks as they sit side by side in the core. Bypass flow is not intentionally designed to occur in the reactor, but is present because of tolerances in manufacture, imperfect installation and expansion and shrinkage of the blocks from heating and irradiation. It is desired to increase the knowledge of the effects of such flow; it has been suggested that it may be 20% of the total helium coolant flow [INL report 2007, INL/EXT-07-13289]. Computational fluid dynamic (CFD) simulations can provide estimates of the scale and impacts of bypass flow. Previous CFD calculations have examined the effects of bypass gap width, level and distribution of heat generation and effects of shrinkage. The present contribution examines the effects of graphite surface roughness on the bypass flow for different relative roughness factors on three gap widths. Such calculations should be validated using specific bypass flow measurements. While such experiments are currently underway for the specific reference prismatic HTGR design for the next generation nuclear plant (NGNP) program of the U.S. Dept. of Energy, the data are not yet available. To enhance confidence in the present calculations, wall shear stress and heat transfer results for several turbulence models and their associated wall treatments are first compared for flow in a single tube that is representative of a coolant channel in the prismatic HTGR core. The results are compared to published correlations for wall shear stress and Nusselt number in turbulent pipe flow. Turbulence models that perform well are then used to make bypass flow calculations in a symmetric one-twelfth sector of a prismatic block that includes bypass flow. The comparison of shear stress and Nusselt number results with published correlations constitutes a partial validation of the CFD model. Calculations are also compared to ones made previously using a different CFD code. Results indicate that increasing surface roughness increases the maximum fuel and helium temperatures as do increases in gap width. However, maximum coolant temperature variation due to increased gap width is not changed by surface roughness.

Copyright © 2011 by ASME

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