277
Views
3
CrossRef citations to date
0
Altmetric
Technical Papers

CFD Verification and Validation of Wire-Wrapped Pin Assemblies

, , &
Pages 1325-1336 | Received 06 Dec 2019, Accepted 04 Feb 2020, Published online: 30 Mar 2020

References

  • A. E. BRIDGES et al., “A Liquid-Metal Reactor Core Demonstration Experiment Using HT-9,” Nucl. Technol., 102, 3, 353 (1993); https://doi.org/10.13182/NT93-A17034.
  • E. U. KHAN, “LMFBR In-Core Thermal-Hydraulics: The State of the Art and U.S. Research and Development Needs,” PNL-3337, Battelle Pacific Northwest Laboratory/U.S. Department of Energy (1980).
  • Y. B. CHEN, K. IP, and N. E. TODREAS, “Velocity Measurements in Edge Subchannels of Wire Wrapped LMFBR Fuel Assemblies,” COO-2245-11TR, Massachusetts Institute of Technology, Department of Nuclear Engineering (1974).
  • M. H. FONTANA et al., “ Temperature Distribution in a 19-Rod Simulated LMFBR Fuel Assembly in a Hexagonal Duct (Fuel Failure Mockup Bundle 2A): Record of Experimental Data,” ORNL-TM-4113, Oak Ridge National Laboratory (1973).
  • T. OHTAKE, S. URUWASHI, and K. TAKAHASHI, “Velocity Measurements in the Subchannel of the Wire-Spaced Subassembly,” Nucl. Technol., 30, 3, 333 (1975); https://doi.org/10.13182/NT76-A31648.
  • B. MAYS and R. B. JACKSON, “Thermal Hydraulic Computational Fluid Dynamics Simulations and Experimental Investigation of Deformed Fuel Assemblies,” AREVA Federal Services/U.S. Department of Energy (2017); https://doi.org/10.2172/1346027.
  • R. HU and T. H. FANNING, “Development of a Three-Dimensional Momentum Source Model for Wire-Wrapped Rod Bundles,” Proc. 14th Int. Topl. Mtg. Nuclear Reactor Thermal-Hydraulics (NURETH-14), Toronto, Ontario, Canada, 2011.
  • W. OBERKAMPF and C. ROY, Verification and Validation in Scientific Computing, Cambridge University Press, New York (2010).
  • STAR-CCM+ User Guide,” CD-ADAPCO (2015).
  • S. KLINE and F. A. McClINTOCK, “Describing Uncertainties in Single-Sample Experiments,” Mech. Eng., 75, 3 (1953).
  • S. K. CHENG and N. E. TODREAS, “Hydrodynamic Models and Correlations for Bare and Wire-Wrapped Hexagonal Rod Bundles—Bundle Friction Factors, Subchannel Friction Factors and Mixing Parameters,” Nucl. Eng. Des., 92, 227 (1986); https://doi.org/10.1016/0029-5493(86)90249-9.

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.