CFD analysis of the impact of a novel spacer grid with longitudinal vortex generators on the sub-channel flow and heat transfer of a rod bundle

Wu, Junmei; Zhu, Fengjie; Lei, Jiang

doi:10.1016/j.nucengdes.2017.08.029

Cited by 15 publications

(7 citation statements)

References 24 publications

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“…The pressure loss due to presence of grid spacer is in a reasonable range compared with Rehme's data [1]. A similar approach with Wu et al [31] was chosen to specify the pressure loss of split mixing vane in this study. The pressure loss due to split mixing vane is approximately 2.1 KPa.…”

Section: Pressure Drop Calculationmentioning

confidence: 89%

“…From z = 100-130 mm, where the spacer grid is located, the pressure drops rapidly due to the local hydraulic resistance of the spacer grid. This result may be explained by the fact that the presence of the spacer grid reduces the flow cross-sectional area, increases the fluid velocity between the grid straps and rods, and results in extra wall frictional resistance of straps [31]. Between 130 mm and 135 mm where the split mixing vane is located, the pressure suddenly decreases due to local resistance of mixing vane.…”

Section: Pressure Drop Calculationmentioning

confidence: 99%

“…Schikorr et al [14] improved Rehme's correlation include grid spacers with mixing devices based on new pressure drop measurements. Morovere, recent studies [15][16][17][18][19][20][21][22][23][24][25][26][27][28][29][30][31] have reported that the mixing vanes cause cross and THERMAL SCIENCE: Year 2019, Vol. 23,No.…”

Section: Introductionmentioning

confidence: 99%

“…The pressure drop depends on the grid spacer and mixing vane design. Numerous studies have showed [13,28,30,31] that the addition of mixing vane on the grid spacer generates more anisotropic axial swirling pattern compared against the standard grid spacer. Nematollahi and Nazifi [13] showed that the standard split mixing vane is expected to significantly enhance the overall heat transfer of a nuclear fuel assembly by 9.82% with a reasonable increase in the pumping cost.…”

Section: Introductionmentioning

confidence: 99%

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Computational fluid dynamic simulation of swirl flow in hexagonal rod bundle geometry by split mixing vane grid spacers

Nazififard

2019

THERM SCI

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Heat transfer and pressure drop are numerically investigated for turbulent flows through a hexagonal fuel rod bundle. For the purpose of numerical analysis, the geometric and boundary conditions were taken from the VVER-1000. Since VVER-1000 does not have mixing vane on the grid spacer of the fuel assembly, split mixing vane is designed to boost turbulent flow and heat transfer in the rod bundle subchannels. The computational domain including two grid spacers extend from 100 × D h upstream of the first grid spacer to 250 × D h downstream of the second grid spacer. The steady-state form of the RANS, mass, energy and turbulence equations was discretized and solved using ANSYS-CFX. The standard k-ε model is employed to simulate turbulence. The results show a considerable increase in the average heat transfer to ~10 × D h downstream of the grid spacer using the mixing vane on the grid spacer of VVER type reactor. As expected, the pressure loss through the grid spacer also increased slightly with the mixing vanes.

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Section: Pressure Drop Calculationmentioning

confidence: 89%

Section: Pressure Drop Calculationmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Computational fluid dynamic simulation of swirl flow in hexagonal rod bundle geometry by split mixing vane grid spacers

Nazififard

2019

THERM SCI

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“…The pressure wave that was generated by the turbulent flow in the nuclear power reactors and the impacts of the external force were assumed to be of impulsive plane wave [20][21][22]. It is difficult to predict the magnitude of the pressure wave in real operating condition.…”

Section: External Force Induced By the Pressure Wavementioning

confidence: 99%

Flexural Vibration Analysis of Nuclear Fuel Rod Bundles Interacting with Surrounding Fluid Subjected to Pressure Wave

2020

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The structural behavior of the nuclear rod bundles that consisted of cylindrical beams was predicted using the spectral element method (SEM) while considering the interaction with the surrounding fluid. Viscous fluid behavior was utilized in order to calculate the forces acting on the nuclear rod bundles from the incident pressure waves. The added mass and fluid coupling on the nuclear rod bundles were determined for the position patterns and gaps of each of the cylindrical beams. The pressure field from propagating waves in the surrounding fluid was calculated with respect to the boundary conditions of the surface of the vibrating structures. With the increasing number of nuclear rods and decreasing pressure wavelengths, the structural vibration of the nuclear rod bundles that were induced by the propagating forces affected the scattering events of the pressure field. The frequency response of the nuclear rod bundles from the pressure waves in the water exhibited smaller damping, because the incident pressure wave travels without fluid coupling due to the longer wavelength when compared with distance between rods. The proposed numerical method can be utilized for the detailed design for effective parameters of a supporting system to reduce the vibration of nuclear fuel rod bundles for safety control.

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The numerical simulation and analysis of turbulent flow behavior in 5 × 5 fuel rod bundle with split-type mixing vane

Wei

Quintanilla

Chen

et al. 2021

Annals of Nuclear Energy

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CFD analysis of the impact of a novel spacer grid with longitudinal vortex generators on the sub-channel flow and heat transfer of a rod bundle

Cited by 15 publications

References 24 publications

Computational fluid dynamic simulation of swirl flow in hexagonal rod bundle geometry by split mixing vane grid spacers

Computational fluid dynamic simulation of swirl flow in hexagonal rod bundle geometry by split mixing vane grid spacers

Flexural Vibration Analysis of Nuclear Fuel Rod Bundles Interacting with Surrounding Fluid Subjected to Pressure Wave

The numerical simulation and analysis of turbulent flow behavior in 5 × 5 fuel rod bundle with split-type mixing vane

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