Study on the mixing performance of mixing vane grids and mixing coefficient by CFD and subchannel analysis code in a 5×5 rod bundle
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Mixing Vane Grid (MVG) is one of the most important structures in fuel assembly due to its high performance in mixing the coolant and ultimately increasing Critical Heat Flux (CHF), which avoids the temperature rising suddenly of fuel rods. To evaluate the mixing performance of the MVG, a Total Diffusion Coefficient (TDC) mixing coefficient is defined in the subchannel analysis code. Conventionally, the TDC of the spacer grid is obtained from the combination of experiments and subchannel analysis. However, the processing of obtaining and determine a reasonable TDC is much challenging, it is affected by boundary conditions and MVG geometries. In is difficult to perform all the large and costing rod bundle tests. In this paper, the CFD method was applied in TDC analysis. A typical 5 5 MVG was simulated and validated to estimate the mixing performance of the MVG. The subchannel code was used to calculate the TDC. Firstly, the CFD method was validated from the aspect of pressure drop and lateral temperature distribution in the subchannels. Then the effect of boundary conditions including the inlet temperature, inlet velocities, heat flux ratio between hot and cold rods and the arrangement of hot and cold rods on MVG mixing and TDC were studied. The geometric effects on mixing are also carried out in this paper. The effect of vane pattern on mixing was investigated to determine which one is the best to represent the grid's mixing performance.
Abstract
Mixing Vane Grid (MVG) is one of the most important structures in fuel assembly due to its high performance in mixing the coolant and ultimately increasing Critical Heat Flux (CHF), which avoids the temperature rising suddenly of fuel rods. To evaluate the mixing performance of the MVG, a Total Diffusion Coefficient (TDC) mixing coefficient is defined in the subchannel analysis code. Conventionally, the TDC of the spacer grid is obtained from the combination of experiments and subchannel analysis. However, the processing of obtaining and determine a reasonable TDC is much challenging, it is affected by boundary conditions and MVG geometries. In is difficult to perform all the large and costing rod bundle tests. In this paper, the CFD method was applied in TDC analysis. A typical 5 5 MVG was simulated and validated to estimate the mixing performance of the MVG. The subchannel code was used to calculate the TDC. Firstly, the CFD method was validated from the aspect of pressure drop and lateral temperature distribution in the subchannels. Then the effect of boundary conditions including the inlet temperature, inlet velocities, heat flux ratio between hot and cold rods and the arrangement of hot and cold rods on MVG mixing and TDC were studied. The geometric effects on mixing are also carried out in this paper. The effect of vane pattern on mixing was investigated to determine which one is the best to represent the grid's mixing performance.
참고문헌 (22)
- N. Cao, "Experimental research on mixing coefficient of fuel assembly in single-phase", Nucl. Power Eng, 30(5), pp.22~25 (2009)
- Crossflow Mixing between Parallel Flow Channels during Boiling. Part Ii. Measurement of Flow and Enthalpy in Two Parallel channels, "D. S. Rowe", Pacific Northwest Lab, ~ (1967)
- Crossflow Mixing between Parallel Flow Channels during Boiling. Part Iii. Effect of Spacers on Mixing between Two channels, "D. S. Rowe", Pacific Northwest Lab, ~ (1969)
- F. Castellana, "Subchannel flow and enthalpy distributions at the exit of a typical nuclear fuel core geometry", Nucl. Eng. Des, 22(1), pp.19~27 (1972)
- F. Castellana, "Single-phase subchannel mixing in a simulated nuclear fuel assembly", Nucl. Eng. Des, 26(2), pp.242~249 (1974)
- Effect of Axial Spacing on Interchannel Thermal Mixing with the R Mixing Vane Grid, "F. F. Cadek", Westinghouse Electric Corp, ~ (1975)
- Effect of 17x17 Fuel Assembly Geometry on Interchannel Thermal Mixing, "F.E. Motley", Westinghouse Electric Corp, ~ (1975)
- J. W. Winters, "AP1000 Design Control Document 18", ~ (2008)
- C. Cheng, "Experimental research of geometrical parameters influencing factor on fuel assembly mixing characteristics", Ann. Nucl. Energy, 164, pp.108634~ (2021)
- A. Liu, "Turbulent mixing models and other mixing coefficients in subchannel codesda review Part A : single phase", Nucl. Technol, 206(9), pp.1253~1295 (2020)
- Maria Avramova, "Development of an Innovative Spacer Grid Model Utilizing Computational Fluid Dynamics within a Subchannel Analysis tool", PhD, pp.2007
- Bostjan Koncar, "Simulation of turbulent flow in MATIS-H rod bundle with split-type mixing vanes", Nucl. Eng. Des, 327, pp.112~126 (2017)
- M. E. Conner, "CFD methodology and validation for single-phase flow in PWR fuel assemblies", Nucl. Eng. Des, 240(9), pp.2088~2095 (2010)
- B. W. Yang, "CFD analysis on mixing effects of spacer grids with different dimples and sizes for advanced fuel assemblies", Kerntechnik, 81(3), pp.221~232 (2016)
- D. Chen, "Thermalehydraulic performance of a 5 5 rod bundle with spacer grid in a nuclear reactor", Appl. Therm. Eng, 103, pp.1416~1426 (2016)
- V. Y. Agbodemegbe, "Correlation for cross-flow resistance coefficient using STAR-CCMþ simulation data for flow of water through rod bundle supported by spacer grid with split-type mixing vane", Nucl. Eng. Des, 285, pp.134~149 (2015)
- Bostjan Koncar, "Simulation of turbulent flow in MATIS-H rod bundle with split-type mixing vanes", Nucl. Eng. Des, 327, pp.112~126 (2017)
- W. Chen, "Mixing performance analysis for advanced fuel assembly grid", Nucl. Power Eng, 29(3), pp.1~4 (2008)
- Hui Zhang, "Numerical Study on the Effects of Vane Angle and Dimple on the Thermal Hydraulic Performance of a PWR Fuel Assembly", the 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) (2015)
- B. Han, "The effect of spacer grid critical component on pressure drop under both single and two phase flow conditions", Kerntechnik, 81(3), pp.257~267 (2016)
- B. W. Yang, "Progress in rod bundle CHF in the past 40years", Nucl. Eng. Des, 376, pp.111076~ (2021)
- B. W. Yang, "Recent challenges in subchannel thermalhydraulics-CFD modeling, subchannel analysis, CHF experiments, and CHF prediction", Nucl. Eng. Des, 354, pp.110236~ (2019)
