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Research Papers

Sensitivity Studies of Shear Stress Transport Turbulence Model Parameters on the Prediction of Seven-Rod Bundle Benchmark Experiments

[+] Author and Article Information
Cale Bergmann

Department of Mechanical Engineering,
University of Manitoba,
75A Chancellors Circle, Winnipeg, MB R3T 5V6, Canada
e-mail: umbergm5@myumanitoba.ca

S. Ormiston

Department of Mechanical Engineering,
University of Manitoba,
75A Chancellors Circle, Winnipeg, MB R3T 5V6, Canada
e-mail: scott.ormiston@umanitoba.ca

V. Chatoorgoon

Department of Mechanical Engineering,
University of Manitoba,
75A Chancellors Circle, Winnipeg, MB R3T 5V6, Canada
e-mail: vijay.chatoorgoon@umanitoba.ca

1Corresponding author.

Manuscript received April 10, 2015; final manuscript received July 2, 2015; published online December 9, 2015. Assoc. Editor: Thomas Schulenberg.

ASME J of Nuclear Rad Sci 2(1), 011012 (Dec 09, 2015) (10 pages) Paper No: NERS-15-1053; doi: 10.1115/1.4031035 History: Received April 10, 2015; Accepted July 07, 2015

This paper reports the findings of a sensitivity study of parameters in the shear stress transport (SST) turbulence model in a commercial computational fluid dynamics (CFD) code to predict an experiment from the Generation IV International Forum Supercritical-Water-Cooled Reactor (GIF SCWR) 2013–2014 seven-rod subchannel benchmark exercise. This study was motivated by the result of the benchmark exercise that all the CFD codes gave similar results to a subchannel code, which does not possess any sophisticated turbulence modeling. Initial findings were that the CFD codes generally underpredicted the wall temperatures on the B2 case in the region where the flow was supercritical. Therefore, it was decided to examine the effect of various turbulence model parameters to determine if a CFD code using the SST turbulence model could do a better job overall in predicting the wall temperatures of the benchmark experiments. A sensitivity study of seven parameters was done, and changes to two parameters were found to make an improvement.

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Figures

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Fig. 1

Cross section of seven-rod bundle, showing domain that was modeled in this study, along with the planes of symmetry

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Fig. 2

Schematic y–z cross section of the domain, showing inlet, heated section, outlet, location of all six spacers relative to the inlet, and location of the pressure taps. All spacers are of the same length. Dimensions are in mm.

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Fig. 3

Typical x–y cross section showing fluid and solid domains and locations of thermocouples: lines a, b, c, d, and e. All dimensions in mm.

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Fig. 4

Equivalent r–θ coordinate system for describing mesh modification procedure shown on typical x–y cross section of BNSP-6 mesh

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Fig. 5

Total pressure drop percentage difference between each mesh and BNSP-1 mesh versus total nodes

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Fig. 6

Cladding surface temperature RMSRN,T versus total nodes

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Fig. 7

Blind modeling results of cladding surface temperature, compared to case B2 experimental data. Default values for SST coefficients were used.

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Fig. 8

y–z cross section at location of spacer showing reduction in grid spacing in z-direction

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Fig. 9

Blind modeling results of cladding surface temperature with spacers modeled, compared to case B2 experimental data. Default values for SST coefficients were used.

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Fig. 10

Cladding surface temperature from using optimized SST coefficient values, compared to results from using default SST coefficient values and case B2 experimental data

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