To model Generation IV reactor systems in detail, INEEL is currently developing a new thermal hydraulic analysis tool coupling RELAP5-3D / ATHENA© and the computational fluid dynamics (CFD) software, Fluent. One of the first steps in this endeavor is extensive validation and verification (V&V) of Fluent for various situations of interest, such as the abrupt expansion of a gas entering a gas-cooled reactor core. Fluent results were compared to validation data provided by Baughn, et al. on turbulent air flow through an axisymmetric pipe expansion with constant wall heat flux [1] and uniform wall temperature [2]. Fluent peak Nusselt numbers varied 25% from validation data—well outside experimental uncertainties of 5%. However, non-peak Nusselt numbers varied only 10% from validation data and fully-developed Nusselt numbers were in good agreement with widely-accepted empirical relations such as the Dittus-Boelter Correlation.
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10th International Conference on Nuclear Engineering
April 14–18, 2002
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-3598-7
PROCEEDINGS PAPER
One Validation Case of the CFD Software Fluent: Part of the Development Effort of a New Reactor Analysis Tool Available to Purchase
William A. Wieselquist
William A. Wieselquist
North Carolina State University, Winston-Salem, NC
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William A. Wieselquist
North Carolina State University, Winston-Salem, NC
Paper No:
ICONE10-22694, pp. 913-919; 7 pages
Published Online:
March 4, 2009
Citation
Wieselquist, WA. "One Validation Case of the CFD Software Fluent: Part of the Development Effort of a New Reactor Analysis Tool." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 4. Arlington, Virginia, USA. April 14–18, 2002. pp. 913-919. ASME. https://doi.org/10.1115/ICONE10-22694
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