Study on Effect of Rolling Motion on Natural Circulation Flow Instability in Rod Bundle Channel

Cheng Kun; Xian Lin; Ran Xu; Zhou Ke; Yu Na

doi:10.13832/j.jnpe.2024.05.0262

Volume 45 Issue 5

Oct. 2024

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Article Navigation > Nuclear Power Engineering > 2024 > 45(5): 262-268

Cheng Kun, Xian Lin, Ran Xu, Zhou Ke, Yu Na. Study on Effect of Rolling Motion on Natural Circulation Flow Instability in Rod Bundle Channel[J]. Nuclear Power Engineering, 2024, 45(5): 262-268. doi: 10.13832/j.jnpe.2024.05.0262

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Cheng Kun, Xian Lin, Ran Xu, Zhou Ke, Yu Na. Study on Effect of Rolling Motion on Natural Circulation Flow Instability in Rod Bundle Channel[J]. Nuclear Power Engineering, 2024, 45(5): 262-268. doi: 10.13832/j.jnpe.2024.05.0262

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Study on Effect of Rolling Motion on Natural Circulation Flow Instability in Rod Bundle Channel

doi: 10.13832/j.jnpe.2024.05.0262

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2023-10-26
Rev Recd Date: 2023-12-16
Publish Date: 2024-10-14

Abstract

Abstract

In order to obtain the influence of rolling motion condition on the natural circulation flow stability, the natural circulation loop experimental system with a rod bundle heating channel is used to carry out a comparative experimental study of flow instability under static and rolling conditions. The experimental results show that the flow instability existing in the rod bundle channel is density wave oscillation (DWO). An empirical correlation for the DWO boundary prediction at low pressure NC condition is obtained. Two typical two-phase flow instabilities in rod bundle channel under rolling condition are found in experiments: the trough-type oscillation caused by the vapor generation at the lowest point of flow fluctuation and the compound oscillation formed by the superposition of the trough-type oscillation and DWO. The evolution law of flow instability behavior of natural circulation under the influence of rolling as well as its instability boundary are also obtained.
- Flow instability,
- Rolling motion,
- Natural circulation,
- Rod bundle channel

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References(7)

References

[1]	YAN B H. Review of the nuclear reactor thermal hydraulic research in ocean motions[J]. Nuclear Engineering and Design, 2017, 313: 370-385. doi: 10.1016/j.nucengdes.2016.12.041
[2]	CHENG K, MENG T, ZHAO F L, et al. Development and validation of a thermal hydraulic transient analysis code for offshore floating nuclear reactor based on RELAP5/SCDAPSIM/MOD3.4[J]. Annals of Nuclear Energy, 2019, 127: 215-226. doi: 10.1016/j.anucene.2018.12.004
[3]	TANG Y, CHEN B D, XIONG W Y, et al. Comparison of flow instabilities under static condition and marine motion conditions based on experiments[J]. Annals of Nuclear Energy, 2014, 70: 11-20. doi: 10.1016/j.anucene.2014.02.010
[4]	LIU D, TIAN W X, XI M M, et al. Study on safety boundary of flow instability and CHF for parallel channels in motion[J]. Nuclear Engineering and Design, 2018, 335: 219-230. doi: 10.1016/j.nucengdes.2018.05.024
[5]	TAN S C, SU G H, GAO P Z. Experimental study on two-phase flow instability of natural circulation under rolling motion condition[J]. Annals of Nuclear Energy, 2009, 36(1): 103-113. doi: 10.1016/j.anucene.2008.09.014
[6]	WANG X Y, TIAN W X, HUANG S Y, et al. Theoretical investigation of two-phase flow instability between parallel channels of natural circulation in rolling motion[J]. Nuclear Engineering and Design, 2019, 343: 257-268. doi: 10.1016/j.nucengdes.2018.12.019
[7]	程坤,谭思超. 海洋条件下反应堆热工水力特性研究进展[J]. 哈尔滨工程大学学报,2019, 40(4): 655-662.

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