High-fidelity numerical simulation of the flow through an infinite wire-wrapped fuel assembly

A. Shams, F. Roelofs, E. M.J. Komen

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

16 Scopus citations

Abstract

The present study is an attempt towards generating a high fidelity reference database for a wire- wrapped fuel assembly of a liquid metal fast reactor (LMFR). This database will be open to the scientific community and will serve to validate RANS based turbulence modelling approaches. In the present paper, the calibration of an infinite wire wrapped fuel assembly is performed for such high fidelity numerical reference simulations. The selection of the fuel assembly has been made on the present MYRRHA design. A wide range of RANS calculations are performed to calibrate the computational domain, boundary conditions, meshing parameters, and the turbulence quantities. This paper also reports the meshing strategy that has been adopted for the reference high fidelity calculations along with some preliminary results obtained from the on-going quasi Direct Numerical Simulation (q-DNS).

Original languageEnglish
Title of host publicationInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
PublisherAmerican Nuclear Society
Pages2817-2829
Number of pages13
ISBN (Electronic)9781510811843
StatePublished - 2015
Externally publishedYes
Event16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 - Chicago, United States
Duration: 30 Aug 20154 Sep 2015

Publication series

NameInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
Volume4

Conference

Conference16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015
Country/TerritoryUnited States
CityChicago
Period30/08/154/09/15

Bibliographical note

Publisher Copyright:
© Copyright (2015) by American Nuclcar Society All rights reserved.

Keywords

  • LMFR
  • MYRRHA
  • Q-DNS
  • RANS
  • Wire-wrapped fuel assembly

ASJC Scopus subject areas

  • Instrumentation
  • Nuclear Energy and Engineering

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