An experimental study of boiling two-phase flow in a vertical rod bundle with a spacer grid. Part 1: Effects of mass flux and heat flux

被引:9
作者
Tas, Sibel [1 ]
Boden, Stephan [1 ]
Franz, Ronald [1 ]
Liao, Yixiang [1 ]
Hampel, Uwe [1 ,2 ]
机构
[1] Helmholtz Zent Dresden Rossendorf, Inst Fluid Dynam, Bautzner Landstr 400, D-01328 Dresden, Germany
[2] Tech Univ Dresden, Chair Imaging Tech Energy & Proc Engn, D-01062 Dresden, Germany
关键词
X-ray computed tomography; Experimental database; Boiling flow; Rod bundle; Void fraction; VOID FRACTION DISTRIBUTION; SUBCHANNEL;
D O I
10.1016/j.expthermflusci.2023.110903
中图分类号
O414.1 [热力学];
学科分类号
摘要
We conducted boiling flow experiments in a 3 x 3 rod bundle containing a spacer grid with split type mixing vanes where the central rod was heated. Void fraction around the spacer grid was measured with high-resolution X-ray computed tomography. The study focusses on the effects of mass and heat flux on the void fraction downstream of the spacer for mass flux and heat flux ranging from 535 to 1950 kg/m2 s and 42.8 to 107.2 kW/ m2, respectively. As the working fluid, refrigerant Octafluorocyclobutane (RC 318) was used and fluid scaling was applied. We found that the void fraction increases as the flow passes through the vanes and then decreases downstream until Z approximate to 4Dh, and then increases again. In addition, we found that the mixing vanes cause a local increase in void fraction even at low heat flux or high mass flux, and that the arrangement of the vanes influences the size and location of the high and low void content regions. We also found that the effect of heat flux on the relative void fraction is more noticeable at high mass flux than at low mass flux. In the second part of the study, which will be presented in a separate paper, we investigated the effect of different vane angles on the void fraction.
引用
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页数:14
相关论文
共 32 条
[1]   PRESSURIZED-WATER REACTOR-FUEL ASSEMBLY SUBCHANNEL VOID FRACTION MEASUREMENT [J].
AKIYAMA, Y ;
HORI, K ;
MIYAZAKI, K ;
MISHIMA, K ;
SUGIYAMA, S .
NUCLEAR TECHNOLOGY, 1995, 112 (03) :412-421
[2]  
Arai T., 2015, RADIAL AXIAL DEV BOI, V27, P203, DOI [10.1615/MultScienTechn.v27.i2-4.70, DOI 10.1615/MULTSCIENTECHN.V27.I2-4.70]
[3]   Void-fraction measurement with high spatial resolution in a 5 x 5 rod bundle by linear-accelerator-driven X-ray computed tomography over a wide pressure range [J].
Arai, Takahiro ;
Furuya, Masahiro ;
Takiguchi, Hiroki ;
Nishi, Yoshihisa ;
Shirakawa, Kenetsu .
FLOW MEASUREMENT AND INSTRUMENTATION, 2019, 69
[4]   Development of a subchannel void sensor and two-phase flow measurement in 10 x 10 rod bundle [J].
Arai, Takahiro ;
Furuya, Masahiro ;
Kanai, Taizo ;
Shirakawa, Kenetsu .
INTERNATIONAL JOURNAL OF MULTIPHASE FLOW, 2012, 47 :183-192
[5]   Experimental investigations of single and two-phase flow in a heated rod bundle [J].
Barthel, F. ;
Franz, R. ;
Hampel, U. .
KERNTECHNIK, 2013, 78 (01) :60-67
[6]   Studies on the subcooled boiling in a fuel assembly with 5 by 5 rods using an improved wall boiling model [J].
Cong, Tenglong ;
Zhang, Rui ;
Chen, Lijuan ;
Zhang, Xiang ;
Yu, Ting .
ANNALS OF NUCLEAR ENERGY, 2018, 114 :413-426
[7]   PRACTICAL CONE-BEAM ALGORITHM [J].
FELDKAMP, LA ;
DAVIS, LC ;
KRESS, JW .
JOURNAL OF THE OPTICAL SOCIETY OF AMERICA A-OPTICS IMAGE SCIENCE AND VISION, 1984, 1 (06) :612-619
[8]   Three dimensional void distribution measurement of salt-water pool-boiling in 5 x 5 bundle geometry with X-ray CT system [J].
Furuya, Masahiro ;
Takiguchi, Hiroki ;
Okawa, Riichiro ;
Arai, Takahiro .
ANNALS OF NUCLEAR ENERGY, 2019, 129 :207-213
[9]  
Garnier J., 2001, Multiph. Sci. Technol, V13, P1, DOI DOI 10.1615/MULTSCIENTECHN.V13.I1-2.10
[10]   Experimental study on local interfacial parameters in upward air-water bubbly flow in a vertical 6 x 6 rod bundle [J].
Han, Xu ;
Shen, Xiuzhong ;
Yamamoto, Toshihiro ;
Nakajima, Ken ;
Sun, Haomin ;
Hibiki, Takashi .
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2019, 144