A dominant geometrical parameter affecting the turbulent mixing rate in rod bundles

Jeong, Hae-Yong; Ha, Kwang Soon; Kwon, Young-Hyuk; Lee, Yongbum; Hahn, Dohee

doi:10.1016/j.ijheatmasstransfer.2006.08.023

Cited by 48 publications

(7 citation statements)

References 17 publications

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“…Due to the large uncertainties and discrepancies among various correlations in the literature, the cross-flow and the turbulent mixing models in the rod bundles are of primary interest in this work. As shown in Figure 3 [6], large discrepancies were found among various correlations for the mixing Stanton number. It is highly dependent on the channel geometry yet many existing correlation are geometry independent.…”

Section: Requirements For the If Modeling Methodsmentioning

confidence: 92%

Progress report on development of intermediate fidelity full assembly analysis methods.

Hu¹,

Fanning²

2011

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While high fidelity modeling capabilities for various physics phenomena are being pursued under advanced modeling and simulation initiatives under the DOE Office of Nuclear Energy, they generally rely on high-performance computation facilities and are too expensive to be used for parameter-space exploration or design analysis. Onedimensional system codes have been used for a long time and have reached a degree of maturity, but limit their validity to specific applications. Thus, an intermediate fidelity (IF) modeling method is being pursued in this work for a fast-running, modest-fidelity, whole-core transient analyses capability. The new approach is essential for design scoping and engineering analyses and could lead to improvements in the design of the new generations of reactors and to the reduction of uncertainties in safety analysis.This report summarizes the initial effort on the development of the intermediatefidelity full assembly modeling method. The requirements and the desired merits of the IF approach have been defined. A three-dimensional momentum source model has been developed to model the anisotropic flow in the wire-wrapped rod bundle without the need to resolve the geometric details. It has been confirmed that the momentum source model works well if its affecting region is accurately imposed. The validity of the model is further verified by mesh and parameter sensitivity studies. The developed momentum source model, in principle, can be applied to any wire-wrapped bundle geometries and any flow regimes; while the modeling strategy can be applied to other conditions with complex or distorted geometry, such as flow in blocked channels.

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Section: Requirements For the If Modeling Methodsmentioning

confidence: 92%

Progress report on development of intermediate fidelity full assembly analysis methods.

Hu¹,

Fanning²

2011

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“…Walls: They are all smooth walls with the no-slip condition. The heat flux on the fuel rod surface is 6 10 W/m^2 based on the operating condition of the SCWR [17].…”

Section: Configurations Of the Channelsmentioning

confidence: 99%

“…Many researchers have investigated the turbulent mixing rate of the fluids in channels. Jeong et al [6] defined a new mixing factor and then evaluated all the experimental data from previous researchers on the turbulent mixing. It was found that the turbulent mixing of fluids depends strongly on the ratio of the distance between the center of two adjacent sub-channels and the hydraulic diameter of a sub-channel.…”

Section: Introductionmentioning

confidence: 99%

Numerical Simulation of Fluid Flow and Heat Transfer of the Supercritical Water in Different Fuel Rod Channels

Han¹,

Zhang²

2018

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The supercritical water-cooled reactor was proposed as one of the Generation IV nuclear systems. Although many research works on the fluid flow and heat transfer of supercritical water in circular channels have been conducted, there is still lack of research on the fluid flow and heat transfer process in fuel bundles used in supercritical water-cooled nuclear reactors. Besides, fuel bundles have multiple fuel rods, the flow is an external flow, not internal flow as that in circle channels, which will cause the difference in the fluid flow phenomenon and heat transfer on the fuel rod cladding surface. In this work, the heat transfer and fluid flow characteristics of the supercritical water in the single-rod channel and the multi-rod channel are simulated numerically. The results show that there are secondary flows in both channels. The circumferential cladding surface temperature variation is large and should be considered in the future fuel rod design. With the same flow rate and heat flux input, the maximum cladding surface temperature in the multi-rod channel is much higher than that in the single-rod channel. Since the maximum cladding surface temperature is an important parameter for the safety of the nuclear reactor operation, it is recommended to use the multi-rod channel model to conduct numerical simulations for the fluid flow and heat transfer of the supercritical water in the Canadian SCWR.

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“…Friction coefficient: Blasius correlation [11] for single phase turbulent flow: Turbulent mixing factor: Rowe and Angle correlation [13] in the bundle condition:…”

Section: Energy Considermentioning

confidence: 99%

Subchannel Analysis of Wire Wrapped SCWR Assembly

Shan

Liu

Song

et al. 2014

Science and Technology of Nuclear Installations

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Application of wire wrap spacers in SCWR can reduce pressure drop and obtain better mixing capability. As a consequence, the required coolant pumping power is decreased and the coolant temperature profile inside the fuel bundle is flattened which will obviously decrease the peak cladding temperature. The distributed resistance model for wire wrap was developed and implemented in ATHAS subchannel analysis code. The HPLWR wire wrapped assembly was analyzed. The results show that: (1) the assembly with wire wrap can obtain a more uniform coolant temperature profile than the grid spaced assembly, which will result in a lower peak cladding temperature; (2) the pressure drop in a wire wrapped assembly is less than that in a grid spaced assembly, which can reduce the operating power of pump effectively; (3) the wire wrap pitch has significant effect on the flow in the assembly. SmallerHwire/Drodwill result in stronger cross flow a more uniform coolant temperature profile, and also a higher pressure drop.

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A dominant geometrical parameter affecting the turbulent mixing rate in rod bundles

Cited by 48 publications

References 17 publications

Progress report on development of intermediate fidelity full assembly analysis methods.

Progress report on development of intermediate fidelity full assembly analysis methods.

Numerical Simulation of Fluid Flow and Heat Transfer of the Supercritical Water in Different Fuel Rod Channels

Subchannel Analysis of Wire Wrapped SCWR Assembly

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