Comparison of experimental and simulation results on interior subchannels of a 61-pin wire-wrapped hexagonal fuel bundle

Journal Article · Wed Aug 22 00:00:00 EDT 2018 · Nuclear Engineering and Design

DOI:https://doi.org/10.1016/j.nucengdes.2018.08.002· OSTI ID:1488543

Goth, N. ^[1]; Jones, P. ^[1]; Nguyen, D. T. ^[1]; Vaghetto, R. ^[1]; Hassan, Y. A. ^[1]; Obabko, A. ^[2]; Merzari, E. ^[2]; Fischer, P. F. ^[3]

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1. Texas A & M Univ., College Station, TX (United States)
2. Argonne National Lab. (ANL), Argonne, IL (United States)
3. Argonne National Lab. (ANL), Argonne, IL (United States); University of Illinois at Urbana-Champaign, Urbana, IL (United States)

As part of a joint U.S. Department of Energy project, Framatome, Argonne National Laboratory, Terrapower, and Texas A&M University have collaborated to produce experimental data and computational results to characterize the flow behavior of a 61-pin wire-wrapped hexagonal fuel bundle. Here, comparisons are made between Texas A&M’s experimental particle image velocimetry velocity field measurements and Argonne National Laboratory’s large-eddy simulation results in an interior subchannel for a Reynolds number of 19,000. It can be concluded that the shape and magnitude of the mean vertical velocity component is in excellent agreement for the selected horizontal line plots. Maximum relative errors are less than 10% until the subchannel walls are approached. Finally, the shape and, to a lesser extent, magnitude of the mean horizontal velocity component is in satisfactory agreement between the particle image velocimetry and large-eddy simulation results.

• Research Organization: Argonne National Laboratory (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE; USDOE Office of Nuclear Energy (NE)
• Grant/Contract Number: AC02-06CH11357; NE0008321; NE0008652
• OSTI ID: 1488543
• Alternate ID(s): OSTI ID: 1701804; OSTI ID: 22836959
• Journal Information: Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Journal Issue: C Vol. 338; ISSN 0029-5493
• Publisher: Elsevier
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
42 ENGINEERING
Comparison of experimental and simulation results
Flow characterization
Hexagonal fuel bundle
Sodium cooled fast reactor
Thermal hydraulics