Preliminary studies of coolant by-pass flows in a prismatic very high temperature reactor using computational fluid dynamics

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Three dimensional computational fluid dynamic (CFD) calculations of a typical prismatic very high temperature gas-cooled reactor (VHTR) were conducted to investigate the influence of gap geometry on flow and temperature distributions in the reactor core using commercial CFD code FLUENT. Parametric calculations changing the gap width in a whole core length model of fuel and reflector columns were performed. The simulations show the effects of core by-pass flows in the heated core region by comparing results for several gap widths including zero gap width. The calculation results underline the importance of considering inter-column gap width for the evaluation of maximum ... continued below

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Sato, Hiroyuki; Johnson, Richard & Schultz, Richard September 1, 2009.

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Three dimensional computational fluid dynamic (CFD) calculations of a typical prismatic very high temperature gas-cooled reactor (VHTR) were conducted to investigate the influence of gap geometry on flow and temperature distributions in the reactor core using commercial CFD code FLUENT. Parametric calculations changing the gap width in a whole core length model of fuel and reflector columns were performed. The simulations show the effects of core by-pass flows in the heated core region by comparing results for several gap widths including zero gap width. The calculation results underline the importance of considering inter-column gap width for the evaluation of maximum fuel temperatures and temperature gradients in fuel blocks. In addition, it is shown that temperatures of core outlet flow from gaps and channels are strongly affected by the gap width of by-pass flow in the reactor core.

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  • 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-13),Kanazawa, Japan,09/27/2009,10/02/2009

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  • Report No.: INL/CON-09-15885
  • Grant Number: DE-AC07-05ID14517
  • Office of Scientific & Technical Information Report Number: 968670
  • Archival Resource Key: ark:/67531/metadc933947

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  • September 1, 2009

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  • Nov. 13, 2016, 7:26 p.m.

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  • Jan. 4, 2017, 2:26 p.m.

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Sato, Hiroyuki; Johnson, Richard & Schultz, Richard. Preliminary studies of coolant by-pass flows in a prismatic very high temperature reactor using computational fluid dynamics, article, September 1, 2009; [Idaho]. (digital.library.unt.edu/ark:/67531/metadc933947/: accessed October 16, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.