Computational Fluid Dynamics (CFD) is applied to steam generator inlet plenum mixing as part of a larger plan covering steam generator tube integrity. The technique is verified by comparing predicted results with severe accident natural circulation data [1] from a 1/7th scale Westinghouse facility. This exercise demonstrates that the technique can predict the natural circulation and mixing phenomena relevant to steam generator tube integrity issues. The model includes primary side flow paths for a single hot leg and steam generator. Qualitatively, the experimentally observed flow phenomena are predicted. The paths of the natural circulation flows and the relative flow proportions are correctly predicted. Quantitatively, comparisons are made with temperatures, mass flows, and other parameters. All predictions are generally within 10% of the experimental values. Overall, there is a high degree of confidence in the CFD technique for prediction of the relevant flow phenomena associated with this type of severe accident sequence.
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10th International Conference on Nuclear Engineering
April 14–18, 2002
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-3597-9
PROCEEDINGS PAPER
CFD Predictions of Severe Accident Steam Generator Flows in a 1/7th Scale Pressurized Water Reactor
Christopher Boyd,
Christopher Boyd
U.S. Nuclear Regulatory Commission, Washington, D.C.
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Kelly Hardesty
Kelly Hardesty
U.S. Nuclear Regulatory Commission, Washington, D.C.
Search for other works by this author on:
Christopher Boyd
U.S. Nuclear Regulatory Commission, Washington, D.C.
Kelly Hardesty
U.S. Nuclear Regulatory Commission, Washington, D.C.
Paper No:
ICONE10-22466, pp. 809-815; 7 pages
Published Online:
March 4, 2009
Citation
Boyd, C, & Hardesty, K. "CFD Predictions of Severe Accident Steam Generator Flows in a 1/7th Scale Pressurized Water Reactor." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 3. Arlington, Virginia, USA. April 14–18, 2002. pp. 809-815. ASME. https://doi.org/10.1115/ICONE10-22466
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