Computational fluid dynamics prediction of grid spacer thermal-hydraulic performance with comparison to experimental results

Robert L. Campbell, John M. Cimbala, Lawrence E. Hochreiter

Research output: Contribution to journalArticle

3 Scopus citations

Abstract

The thermal-hydraulic performance of a nuclear reactor fuel assembly grid spacer is predicted using computational fluid dynamics. The modeled flow domain exploits the periodicity of the spacer and is separated into a bare bundle and grid region to maintain a manageable model size. An iterative process is used to couple the segregated flow domains to arrive at a converged solution. The grid spacer is a 7 × 7 mixing vane grid representative of an actual pressurized water reactor grid. Pressure drop and rod wall temperature predictions for steady-state operation are computed. The results show excellent agreement with experimental data. The agreement in these results demonstrates the usefulness of the method presented as a design tool for nuclear fuel manufacturers and as a prediction tool for off-design operating conditions such as simulated accident scenarios.

Original languageEnglish (US)
Pages (from-to)49-61
Number of pages13
JournalNuclear Technology
Volume149
Issue number1
DOIs
StatePublished - Jan 2005

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering
  • Condensed Matter Physics

Fingerprint Dive into the research topics of 'Computational fluid dynamics prediction of grid spacer thermal-hydraulic performance with comparison to experimental results'. Together they form a unique fingerprint.

  • Cite this