Published 2011 | Version v1
Miscellaneous

Coarse-Grid-CFD for pressure loss evaluation in rod bundles

  • 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)

Part of:
Proceedings of ICAPP 2011

Additional details

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/