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NPHASE predictions of turbulent flow in the lower plenum of a prismatic gas-cooled reactor

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3 Scopus citations

Abstract

This paper is concerned with the implementation of a computational model of turbulent flow in a section of the lower plenum of Very High Temperature Reactor (VHTR). The proposed model has been encoded in a state-of-the-art CFD code, NPHASE. The results of NPHASE predictions have been compared against the experimental data collected using a scaled model of a sub-region in the lower plenum of a modular prismatic gas-cooled reactor, GT-MHR. It has been shown that the NPHASE-based model is capable of predicting a three-dimensional velocity field in a complex geometrical configuration of VHTR lower plenum. This, in turn, demonstrates the potential of detailed CFD simulations as a tool for the design and safety analysis of new reactor concepts.

Original languageEnglish
Title of host publicationProceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12
StatePublished - 2007
Event12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12 - Pittsburgh, PA, United States
Duration: Sep 30 2007Oct 4 2007

Publication series

NameProceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12

Conference

Conference12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12
Country/TerritoryUnited States
CityPittsburgh, PA
Period09/30/0710/4/07

Keywords

  • Gas-cooled reactor
  • Multidimensional simulations of fluid flow
  • NPHASE code

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