棒束通道内定位格架搅混特性PIV可视化研究
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摘要
定位格架作为燃料组件中重要的组成部件之一,不仅在结构上固定燃料棒,而且在燃料组件内热工水力性能同样显著,特别是对工质的搅混性能直接关系到反应堆的经济性和安全性,因此有必要对燃料组件内定位格架搅混特性进行研究。本文通过粒子图像测速(PIV)技术开展了棒束通道内定位格架上下游流场的可视化研究,对比了有无格架棒束通道内流场的分布特征,定量分析了定位格架对棒束通道流场搅混的贡献。对不同流速下定位格架下游横纵速度的沿程变化特性进行研究,发现了不同流速作用下定位格架对横向、轴向速度的促进和抑制规律。另外,通过速度均方根对下游的湍流特性进行了评估。实验结果可为数值计算提供全场的数据验证,并可为定位格架设计和优化提供基础。
Spacer grid is one of important components in fuel assembly. Not only do spacer grids provide rods with supporting and positioning, but also their thermal hydraulic performance is significant in fuel assembly. The cross-mixing of spacer grid for the working fluid is closely related to the economy and safety of reactor. Therefore, an investigation on mixing characteristic of spacer grids in fuel assembly is indispensable. A visualization research on flow field upstream and downstream the spacer grid was implemented by the particle image velocimetry(PIV) technique. In order to obtain a global understanding of mixing characteristic of spacer grids, comparisons of the velocity distribution in a rod bundle with and without spacer grids were performed, and the mixing contribution of spacer grids for flow field was quantitatively evaluated. The lateral velocity and axial velocity downstream the spacer grid for the different inlet boundary conditions were obtained, and mixing characteristics of spacer grids for lateral velocity and axial velocity were analyzed under different flows. In addition, the turbulence characteristics downstream the spacer grid were assessed. Experimental results benefit the development and evaluation of spacer grid, and also provide the whole-field validation for numerical simulations.
Spacer grid is one of important components in fuel assembly. Not only do spacer grids provide rods with supporting and positioning, but also their thermal hydraulic performance is significant in fuel assembly. The cross-mixing of spacer grid for the working fluid is closely related to the economy and safety of reactor. Therefore, an investigation on mixing characteristic of spacer grids in fuel assembly is indispensable. A visualization research on flow field upstream and downstream the spacer grid was implemented by the particle image velocimetry(PIV) technique. In order to obtain a global understanding of mixing characteristic of spacer grids, comparisons of the velocity distribution in a rod bundle with and without spacer grids were performed, and the mixing contribution of spacer grids for flow field was quantitatively evaluated. The lateral velocity and axial velocity downstream the spacer grid for the different inlet boundary conditions were obtained, and mixing characteristics of spacer grids for lateral velocity and axial velocity were analyzed under different flows. In addition, the turbulence characteristics downstream the spacer grid were assessed. Experimental results benefit the development and evaluation of spacer grid, and also provide the whole-field validation for numerical simulations.
引文
[1] 阎昌琪. 核反应堆工程[M]. 哈尔滨:哈尔滨工程大学出版社,2014.
[2] 杜光彦,张世权. 压水堆燃料组件方形定位格架结构设计、工艺特点和性能评价[J]. 核动力工程,1987,8(3):67-75. DU Guangyan, ZHANG Shiquan. The structure design, technology characteristics and performance evaluation for square spacer grid of PWR fuel assembly[J]. Nuclear Power Engineering, 1987, 8(3): 67-75(in Chinese).
[3] LI Xiaochang, GAO Ye. Methods of simulating large-scale rod bundle and application to a 17×17 fuel assembly with mixing vane spacer grid[J]. Nuclear Engineering and Design, 2014, 267: 10-22.
[4] LIU C C, FERNG Y M, SHIH C K. CFD evaluation of turbulence models for flow simulation of the fuel rod bundle with a spacer assembly[J]. Applied Thermal Engineering, 2012, 40(7): 389-396.
[5] PODILA K, RAO Y. CFD modelling of turbulent flows through 5×5 fuel rod bundles with spacer-grids[J]. Annals of Nuclear Energy, 2016, 97: 86-95.
[6] CHEN X, DU S, ZHANG Y, et al. Validation of CFD analysis for rod bundle flow test with vaned spacer grids[J]. Annals of Nuclear Energy, 2017, 109: 370-379.
[7] 晁嫣萌,杨立新,张玉相,等. 湍流模型对5×5格架棒束通道流动传热数值模拟影响分析[J]. 原子能科学技术, 2014,48(10):1 782-1 789. CHAO Yanmeng, YANG Lixin, ZHANG Yu-xiang, et al. CFD evaluation of turbulence model on heat transfer in 5×5 rod bundles[J]. Atomic Energy Science and Technology, 2014, 48(10): 1 782-1 789(in Chinese).
[8] CHANG S K, SANG K M, BAEK W P, et al. Phenomenological investigations on the turbulent flow structures in a rod bundle array with mixing devices[J]. Nuclear Engineering and Design, 2008, 238(3): 600-609.
[9] SZYMANSKI J, CHANG D, NOVOG D, et al. Canadian participation in OECD/NEA-KAERI rod bundle benchmark for CFD codes[C]//The 24th CNS Nuclear Simulation Symposium. Ottawa, Canada: Canadian Nuclear Society, 2012.
[10] CHANG S K, KIM S, SONG C H. Turbulent mixing in a rod bundle with vaned spacer grids: OECD/NEA-KAERI CFD benchmark exercise test[J]. Nuclear Engineering and Design, 2014, 279: 19-36.
[11] LEE J R, KIM J, SONG C H. Synthesis of the turbulent mixing in a rod bundle with vaned spacer grids based on the OECD-KAERI CFD benchmark exercise[J]. Nuclear Engineering and Design, 2014, 279: 3-18.
[12] DOMINGUEZ-ONTIVEROS E, HASSAN Y A. Experimental study of a simplified 3×3 rod bundle using DPTV[J]. Nuclear Engineering and Design, 2014, 279: 50-59.
[13] 田齐伟,阎昌琪,孙立成,等. 棒束通道内两相流动摩擦阻力特性分析[J]. 原子能科学技术,2015,49(5):819-824. TIAN Qiwei, YAN Changqi, SUN Licheng, et al. Analysis of frictional resistance of two-phase flow in rod bundle channel[J]. Atomic Energy Science and Technology, 2015, 49(5): 819-824(in Chinese).
[14] 闫超星,阎昌琪,孙立成,等. 棒束通道内定位格架的两相流动局部阻力实验研究[J]. 原子能科学技术,2015,49(2):279-284. YAN Chaoxing, YAN Changqi, SUN Licheng, et al. Experimental study on local resistance of two-phase flow through spacer grid with rod bundle[J]. Atomic Energy Science and Technology, 2015, 49(2): 279-284(in Chinese).
[15] XIONG J, YU N, YU Y, et al. Experimental investigation on anisotropic turbulent flow in a 6×6 rod bundle with LDV[J]. Nuclear Engineering and Design, 2014, 278: 333-343.
[16] RAFFEL M, WILLERT C, KOMPENHANS J. Particle image velocimetry: A practical guide[M]//2nd edition. Puducherry, India: Integra Software Services Private Limited, 2007: 216.
[17] MARCHIOLI C, ARMENIO V, SALVETTI M V, et al. Mechanisms for deposition and resuspension of heavy particles in turbulent flow over wavy interfaces[J]. Physics of Fluids, 2006, 18: 025102.
[18] NISHIO S, OKAMOTO K, KOBAYASHI T, et al. Evaluation of system performance and uncertainty analysis of PIV[C]//Proceedings of the 3rd International Workshop on Particle Image Velocimetry. Santa Barbara, USA: [s. n.], 1999: 465-470.
[2] 杜光彦,张世权. 压水堆燃料组件方形定位格架结构设计、工艺特点和性能评价[J]. 核动力工程,1987,8(3):67-75. DU Guangyan, ZHANG Shiquan. The structure design, technology characteristics and performance evaluation for square spacer grid of PWR fuel assembly[J]. Nuclear Power Engineering, 1987, 8(3): 67-75(in Chinese).
[3] LI Xiaochang, GAO Ye. Methods of simulating large-scale rod bundle and application to a 17×17 fuel assembly with mixing vane spacer grid[J]. Nuclear Engineering and Design, 2014, 267: 10-22.
[4] LIU C C, FERNG Y M, SHIH C K. CFD evaluation of turbulence models for flow simulation of the fuel rod bundle with a spacer assembly[J]. Applied Thermal Engineering, 2012, 40(7): 389-396.
[5] PODILA K, RAO Y. CFD modelling of turbulent flows through 5×5 fuel rod bundles with spacer-grids[J]. Annals of Nuclear Energy, 2016, 97: 86-95.
[6] CHEN X, DU S, ZHANG Y, et al. Validation of CFD analysis for rod bundle flow test with vaned spacer grids[J]. Annals of Nuclear Energy, 2017, 109: 370-379.
[7] 晁嫣萌,杨立新,张玉相,等. 湍流模型对5×5格架棒束通道流动传热数值模拟影响分析[J]. 原子能科学技术, 2014,48(10):1 782-1 789. CHAO Yanmeng, YANG Lixin, ZHANG Yu-xiang, et al. CFD evaluation of turbulence model on heat transfer in 5×5 rod bundles[J]. Atomic Energy Science and Technology, 2014, 48(10): 1 782-1 789(in Chinese).
[8] CHANG S K, SANG K M, BAEK W P, et al. Phenomenological investigations on the turbulent flow structures in a rod bundle array with mixing devices[J]. Nuclear Engineering and Design, 2008, 238(3): 600-609.
[9] SZYMANSKI J, CHANG D, NOVOG D, et al. Canadian participation in OECD/NEA-KAERI rod bundle benchmark for CFD codes[C]//The 24th CNS Nuclear Simulation Symposium. Ottawa, Canada: Canadian Nuclear Society, 2012.
[10] CHANG S K, KIM S, SONG C H. Turbulent mixing in a rod bundle with vaned spacer grids: OECD/NEA-KAERI CFD benchmark exercise test[J]. Nuclear Engineering and Design, 2014, 279: 19-36.
[11] LEE J R, KIM J, SONG C H. Synthesis of the turbulent mixing in a rod bundle with vaned spacer grids based on the OECD-KAERI CFD benchmark exercise[J]. Nuclear Engineering and Design, 2014, 279: 3-18.
[12] DOMINGUEZ-ONTIVEROS E, HASSAN Y A. Experimental study of a simplified 3×3 rod bundle using DPTV[J]. Nuclear Engineering and Design, 2014, 279: 50-59.
[13] 田齐伟,阎昌琪,孙立成,等. 棒束通道内两相流动摩擦阻力特性分析[J]. 原子能科学技术,2015,49(5):819-824. TIAN Qiwei, YAN Changqi, SUN Licheng, et al. Analysis of frictional resistance of two-phase flow in rod bundle channel[J]. Atomic Energy Science and Technology, 2015, 49(5): 819-824(in Chinese).
[14] 闫超星,阎昌琪,孙立成,等. 棒束通道内定位格架的两相流动局部阻力实验研究[J]. 原子能科学技术,2015,49(2):279-284. YAN Chaoxing, YAN Changqi, SUN Licheng, et al. Experimental study on local resistance of two-phase flow through spacer grid with rod bundle[J]. Atomic Energy Science and Technology, 2015, 49(2): 279-284(in Chinese).
[15] XIONG J, YU N, YU Y, et al. Experimental investigation on anisotropic turbulent flow in a 6×6 rod bundle with LDV[J]. Nuclear Engineering and Design, 2014, 278: 333-343.
[16] RAFFEL M, WILLERT C, KOMPENHANS J. Particle image velocimetry: A practical guide[M]//2nd edition. Puducherry, India: Integra Software Services Private Limited, 2007: 216.
[17] MARCHIOLI C, ARMENIO V, SALVETTI M V, et al. Mechanisms for deposition and resuspension of heavy particles in turbulent flow over wavy interfaces[J]. Physics of Fluids, 2006, 18: 025102.
[18] NISHIO S, OKAMOTO K, KOBAYASHI T, et al. Evaluation of system performance and uncertainty analysis of PIV[C]//Proceedings of the 3rd International Workshop on Particle Image Velocimetry. Santa Barbara, USA: [s. n.], 1999: 465-470.
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