Experimental Study on Critical Heat Flux of Vertical Square Channel with Single Rod

被引：0

作者：

Liu W. ^{[1
]}

Guo J. ^{[2
]}

Zhang D. ^{[1
]}

Gui M. ^{[2
]}

Hu Y. ^{[1
]}

Liu Y. ^{[2
]}

机构：

[1] Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu

[2] School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an

来源：

Hedongli Gongcheng/Nuclear Power Engineering | 2022年 / 43卷 / 01期

关键词：

Critical heat flux(CHF); Experimental study; Square channel;

D O I：

10.13832/j.jnpe.2022.01.0042

中图分类号：

学科分类号：

摘要：

The critical heat flux (CHF) of vertical square channel with single rod is experimentally studied by using R134a as the working fluid. A square channel with a flow channel cross section of 19 mm×19 mm and a single heating rod with an outer diameter of 9.5 mm are used to simulate the typical cell channel in PWR. The experimental conditions cover the typical operating conditions of PWR by fluid modeling method. The experimental results show that the CHF parameter trend of R134a in the square channel is the same as that of water in the circular tube, and R134a can replace water as a modeling fluid; After corrected with cold wall factor, the circular tube Bowring relation and Katto & Ohno relation can be used to predict CHF in square channel with cold wall; Katto's fluid modeling method is suitable for square channel with cold wall. Copyright ©2022 Nuclear Power Engineering. All rights reserved.

引用

页码：42 / 47

页数：5

共 10 条

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