Home / Store / Journals / Electronic Articles / Nuclear Technology / Volume 149 / Number 1 / Pages 49-61
Robert L. Campbell, John M. Cimbala, Lawrence E. Hochreiter
Nuclear Technology / Volume 149 / Number 1 / Pages 49-61
Format:electronic copy (download)
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.
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