Published September 2010 | Version v1
Journal article

A CFD simulation process for fast reactor fuel assemblies

  • 1. Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-3840 (United States)

Description

A CFD modeling and simulation process for large-scale problems using an arbitrary fast reactor fuel assembly design was evaluated. Three-dimensional flow distributions of sodium for several fast reactor fuel assembly pin spacing configurations were simulated on high performance computers using commercial CFD software. This research focused on 19-pin fuel assembly 'benchmark' geometry, similar in design to the Advanced Burner Test Reactor, where each pin is separated by helical wire-wrap spacers. Several two-equation turbulence models including the k-ε and SST (Menter) k-ω were evaluated. Considerable effort was taken to resolve the momentum boundary layer, so as to eliminate the need for wall functions and reduce computational uncertainty. High performance computers were required to generate the hybrid meshes needed to predict secondary flows created by the wire-wrap spacers; computational meshes ranging from 65 to 85 million elements were common. A general validation methodology was followed, including mesh refinement and comparison of numerical results with empirical correlations. Predictions for velocity, temperature, and pressure distribution are shown. The uncertainty of numerical models, importance of high fidelity experimental data, and the challenges associated with simulating and validating large production-type problems are presented.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2009.11.007

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2009.11.007;
PII
S0029-5493(09)00566-4;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
240
Journal Issue
9
Journal Page Range
p. 2304-2312
ISSN
0029-5493
CODEN
NEDEAU

Conference

Title
2. workshop on experiments and CFD code applications to nuclear reactor safety
Acronym
XCFD4NRS
Dates
10-12 Sep 2008
Place
Grenoble (France)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
42014690
Subject category
S42: ENGINEERING;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
BENCHMARKS; BOUNDARY LAYERS; COMPARATIVE EVALUATIONS; COMPUTER-AIDED DESIGN; COMPUTERIZED SIMULATION; COMPUTERS; EXPERIMENTAL DATA; FAST REACTORS; FLUID FLOW; FLUID MECHANICS; FUEL ASSEMBLIES; FUEL PINS; HEAT TRANSFER; SHEAR; SODIUM; SPACERS; STRESSES; THREE-DIMENSIONAL CALCULATIONS; TURBULENCE; WALLS
Descriptors DEC
ALKALI METALS; DATA; DESIGN; ELEMENTS; ENERGY TRANSFER; EPITHERMAL REACTORS; EVALUATION; FUEL ELEMENTS; INFORMATION; LAYERS; MECHANICS; METALS; NUMERICAL DATA; REACTOR COMPONENTS; REACTORS; SIMULATION

Optional Information

Copyright
Copyright (c) 2009 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.