Coarse-Grid-CFD for pressure loss evaluation in rod bundles
Creators
- 1. Karlsruhe Institute of Technology GmbH, Institute for Nuclear and Energy Technologies, P.O. Box 3640, 76021 Karlsruhe (Germany)
Description
CFD simulation of the complete reactor core of a nuclear power plant requires exceedingly huge computational resources so that this crude power approach has not been pursued yet. The traditional approach is the use of one dimensional sub channel analysis, employing calibrated transport models. Coarse-Grid-CFD is an attractive alternative technique based on strongly under-resolved CFD and the inviscid Euler equations. Obviously, using inviscid equations and coarse grids does not resolve all the relevant physics. The neglected physics is restored by additional volumetric source terms modeling viscosity and other sub-grid effects. The source terms are implemented via correlations derived from fully resolved representative simulations. The new simulation technique is demonstrated for a rod bundle experiment performed at the KALLA experiment of the Karlsruhe Institute of Technology (KIT) which includes three spacer grids. In this paper a 3D CFD study of the rod bundle is presented. A representative computational domain of the bundle is selected for the Coarse-Grid-CFD study. Comparison of the 3D CFD results to experimental results shows that a good agreement is obtained by an adequate selection of the computational grid. Coarse-Grid- CFD study results in good agreement with 3D CFD results. Careful selection of the representative coarse grid in geometrically complex regions like spacers is recommended. (authors)
Additional details
Identifiers
Publishing Information
- Imprint Title
- Proceedings of ICAPP 2011
- Imprint Pagination
- 2851 p.
- Journal Page Range
- p. 1773-1780
- Report number
- INIS-FR--13-0283
Conference
- Title
- The Power of Innovation
- Acronym
- ICAPP 2011 - Performance and Flexibility
- Dates
- 2-5 May 2011
- Place
- Nice (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 44092988
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCH-SCALE EXPERIMENTS; FUEL ELEMENT CLUSTERS; LIQUID FLOW; MESH GENERATION; PRESSURE DROP; THREE-DIMENSIONAL CALCULATIONS; VALIDATION; WATER COOLED REACTORS
- Descriptors DEC
- FLUID FLOW; FUEL ASSEMBLIES; REACTORS; TESTING
Optional Information
- Notes
- 7 refs.; Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/INIS/contacts/