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Volume 43 Issue 1
Feb.  2022
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Liu Wei, Guo Junliang, Zhang Dan, Gui Miao, Hu Ying, Liu Yang. Experimental Study on Critical Heat Flux of Vertical Square Channel with Single Rod[J]. Nuclear Power Engineering, 2022, 43(1): 42-47. doi: 10.13832/j.jnpe.2022.01.0042
Citation: Liu Wei, Guo Junliang, Zhang Dan, Gui Miao, Hu Ying, Liu Yang. Experimental Study on Critical Heat Flux of Vertical Square Channel with Single Rod[J]. Nuclear Power Engineering, 2022, 43(1): 42-47. doi: 10.13832/j.jnpe.2022.01.0042

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

doi: 10.13832/j.jnpe.2022.01.0042
  • Received Date: 2020-10-17
  • Rev Recd Date: 2020-11-20
  • Publish Date: 2022-02-01
  • 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.

     

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