Hydraulic resistance of in-tube cooling supercritical water accompanying out-tube pool boiling

被引：4

作者：

Lv, Haicai ^{[1
]}

Bi, Qincheng ^{[1
]}

Zhang, Zanjian ^{[1
]}

Zhu, Ge ^{[1
]}

Li, Kun ^{[1
]}

Liu, Hongyang ^{[1
]}

机构：

[1] Xi An Jiao Tong Univ, State Key Lab Multiphase Flow Power Engn, 28 Xianning West Rd, Xian 710049, Shaanxi, Peoples R China

来源：

APPLIED THERMAL ENGINEERING | 2018年 / 141卷

关键词：

Supercritical water; Hydraulic resistance; Cooling; Deceleration; HEAT REMOVAL SYSTEM; PRESSURE-DROP; COEFFICIENT; CHANNELS; REACTOR; FLUIDS; FLOW;

D O I：

10.1016/j.applthermaleng.2018.04.136

中图分类号：

O414.1 [热力学];

学科分类号：

摘要：

The experiment was conducted by immersing a smooth horizontal tube in a pool tank to simulate the flow condition of Passive Residual Heat Removal System (PRHRS) in a SuperCritical Water-cooled Reactor (SCWR). Hydraulic resistance and friction factor of in-tube cooling supercritical water accompanying out-tube pool boiling were investigated in this study with test pressure ranging from 23 to 28 MPa and mass flux ranging from 600 to 1000 kg-m(-2).s(-1). The influence of pressure and mass flux on pressure drop in adiabatic and cooling flows was analyzed. This paper also discussed the effect of deceleration in the cooling flow and assessed various friction-factor correlations by employing the experimental data. Results showed that the friction factor of the adiabatic flow exists a steep "pit" approaching to pseudocritical region. A noticeable "A-shaped" profile was observed in the vicinity of the pseudocritical temperature, due to deceleration-effect of frictional pressure drop in the cooling flow. The deceleration factor of supercritical cooling flow led to the axial fluid element shrinkage and radial bulk fluid velocity parabolic distribution. Taking into account the effect of deceleration-factor, a modified correlation was proposed for in-tube cooling supercritical water accompanying out-tube pool boiling, of which the average error and root mean square error are -2.51% and 15.28% respectively.

引用

页码：394 / 405

页数：12

共 35 条

[1]

[Anonymous], J THERM SCI, DOI DOI 10.1007/BF02653159

[2]

[Anonymous], 2002, A Technology Roadmap for Generation IV Nuclear Energy Systems

[3] Design and modeling of the passive residual heat removal system for VVERs [J].

Ayhan, Huseyin ;

Sokmen, Cemal Niyazi .

ANNALS OF NUCLEAR ENERGY, 2016, 95 :109-115

[4] Quake sparks nuclear crisis [J].

Brumfiel, Geoff ;

Cyranoski, David ;

Abbott, Alison .

NATURE, 2011, 471 (7338) :273-275

[5] Experimental study on convection heat transfer of R134a at supercritical pressures in a vertical tube for upward and downward flows [J].

Cui, Ya-Lin ;

Wang, Huai-Xin .

APPLIED THERMAL ENGINEERING, 2018, 129 :1414-1425

[6]

Dragunov A, 2014, PROCEEDINGS OF THE ASME INTERNATIONAL MECHANICAL ENGINEERING CONGRESS AND EXPOSITION, 2013, VOL 15

[7] Pressure drop and friction factor correlations of supercritical flow [J].

Fang, Xiande ;

Xu, Yu ;

Su, Xianghui ;

Shi, Rongrong .

NUCLEAR ENGINEERING AND DESIGN, 2012, 242 :323-330

[8]

Filonenko G.K., 1954, Toploenergetika, V1, P40

[9] Investigation of a long term passive cooling system using two-phase thermosyphon loops for the nuclear reactor spent fuel pool [J].

Fu, Wen ;

Li, Xiaowei ;

Wu, Xinxin ;

Zhang, Zhengming .

ANNALS OF NUCLEAR ENERGY, 2015, 85 :346-356

[10] Heat transfer and pressure drop during supercritical cooling of HFC refrigerant blends [J].

Garimella, Srinivas ;

Mitra, Biswajit ;

Andresen, Ulf C. ;

Jiang, Yirong ;

Fronk, Brian M. .

INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2015, 91 :477-493

← 1 2 3 4 →