Laser Doppler measurement and CFD validation in 3×3 bundle flow

Xiong, Juntao; Yu, Yang; Yu, Nan; Fu, Xiaoliang; Wang, Hongyan; Xu, Cheng; Yang, Yanhua

doi:10.1016/j.nucengdes.2014.02.009

Cited by 23 publications

(5 citation statements)

References 4 publications

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“…The experiment and simulation contour are shown in Fig8. [9]. The dimensionless axial velocity is defined as VD=w/W.…”

Section: Rans Simulation Results and Experiments Validationmentioning

confidence: 99%

“…In this paper, a 3x3 rod bundle experiment [9] was used to validate the simulation results. The objective of this paper was to evaluate the turbulence model choice in simulating the flow field around rod bundles of fuel assemble in reactors, and with the aid of experiment validation to find a proper turbulence model for engineering and research.…”

Section: Introductionmentioning

confidence: 99%

“…So the experiment data can also be used to validate CFD methods. The test section is shown in Figure 1 [9]. The bundles' length is 1.5m, their diameter is 9.5mm and the distance between bundles is 3mm.…”

Section: Experiments Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Flow around Nuclear rod bundles' simulations based on RANS and LES method respectively

Yan¹,

Li²

2016

JFFHMT

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“…The experiment and simulation contour are shown in Fig8. [9]. The dimensionless axial velocity is defined as VD=w/W.…”

Section: Rans Simulation Results and Experiments Validationmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Flow around Nuclear rod bundles' simulations based on RANS and LES method respectively

Yan¹,

Li²

2016

JFFHMT

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show abstract

“…Step-by-step experimental activities are on-going in Shanghai Jiao Tong University to provide the high-quality CFD validation data. Experimental measurement of turbulent flow in a 3 × 3 rod bundle is first carried out for CFD validation (Xiong et al, 2014a). Following the 3 × 3 rod bundle experiment, the flow field in the 6 × 6 rod bundle installed with simple ring-type grids is measured with the LDA and utilized for CFD validation (Xiong et al, 2014b).…”

Section: Introductionmentioning

confidence: 99%

Validation for CFD Simulation in Rod Bundles With Split-Vane Spacer Grids Based on LDA Measurement

Xiong

2020

Front. Energy Res.

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Laser Doppler anemometry (LDA) measurement of axial flow velocity and pressure drop measurement has been carried out in a 5 × 5 rod bundle installed with two split-mixing-vane grids. The measured results are utilized to validate the CFD simulation. The realizable and non-linear k-ε turbulence model is utilized in the CFD computation, while the two-layer wall treatment is employed with both models. Mesh sensitivity investigation shows that the pressure drop is weakly affected by local mesh refinement in the spacer grid, while its effect on the velocity in the near wake of spacer grid is apparent. The validation shows that prediction on the mean axial velocity is relatively poor in the near wake of the spacer grid where the measured result shows relatively smooth distribution of axial velocity. Refinement of mesh in the spacer grid eliminates some peaks for the non-linear model. Comparing with the effect of mesh refinement, the difference caused by the turbulence models is relatively weak in the near wake region. In the far-wake region it is still difficult to judge which model shows definite superiority to the other. For pressure drop, prediction of non-linear k-ε is closer to the experiment.

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“…Chang et al, [1] and Xiong et al, [2] utilized a LDV-2D and 3D, respectively, for axial and lateral velocities profiles evaluation of the water flow through a test rig with a mixing vane spacer grids.…”

Section: Introductionmentioning

confidence: 99%

5X5 Rod Bundle Flow Field Measurements Downstream a PWR Spacer Grid

Castro

Silva²,

Santos³

et al. 2020

Braz. J. Rad. Sci.

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The spacer grids are structures present in nuclear fuel assembly of Pressurized Water Reactors (PWR). They play an important structural role and also assist in heat removal through the assembly by promoting increased turbulence of the flow. Understanding the flow dynamics downstream the spacer grid is paramount for fuel element design and analysis. This paper presents water flow velocity profiles measurements downstream a spacer grid in a 5x5 rod bundle test rig with the objective of highlighting important fluid dynamic behavior near the grid and supplying data for CFD simulation validation. These velocity profiles were obtained at two different heights downstream the spacer grid using a LDV (Laser Doppler Velocimetry) through the top of test rig. The turbulence intensities and patterns of the swirl and cross flow were evaluated. The tests were conducted for Reynolds numbers ranging from 1.8x104 to 5.4x104. This experimental research was carried out in thermohydraulics laboratory of Nuclear Technology Development Center – CDTN. Results show great repeatability and low uncertainties (< 1.24 %). Details of the flow field show how the mixture and turbulence induced by the spacer grid quickly decays downstream the spacer grid. It is shown that the developed methodology can supply high resolution low uncertainty results that can be used for validation of CFD simulations.

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Laser Doppler measurement and CFD validation in 3×3 bundle flow

Cited by 23 publications

References 4 publications

Flow around Nuclear rod bundles' simulations based on RANS and LES method respectively

Flow around Nuclear rod bundles' simulations based on RANS and LES method respectively

Validation for CFD Simulation in Rod Bundles With Split-Vane Spacer Grids Based on LDA Measurement

5X5 Rod Bundle Flow Field Measurements Downstream a PWR Spacer Grid

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