Experimental Investigation on Void Fraction Distribution of Boiling Flow in 2×2 Rod Bundle Channel

Liu Hao; Zhang Luteng; Zhou Wenxiong; Zhu Longxiang; Wan Lingfeng; Zhang Hong; Ma Zaiyong; Sun Wan; Pan Liangming; Deng Jiewen

doi:10.13832/j.jnpe.2023.06.0104

Volume 44 Issue 6

Dec. 2023

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Article Navigation > Nuclear Power Engineering > 2023 > 44(6): 104-110

Liu Hao, Zhang Luteng, Zhou Wenxiong, Zhu Longxiang, Wan Lingfeng, Zhang Hong, Ma Zaiyong, Sun Wan, Pan Liangming, Deng Jiewen. Experimental Investigation on Void Fraction Distribution of Boiling Flow in 2×2 Rod Bundle Channel[J]. Nuclear Power Engineering, 2023, 44(6): 104-110. doi: 10.13832/j.jnpe.2023.06.0104

Citation:

Liu Hao, Zhang Luteng, Zhou Wenxiong, Zhu Longxiang, Wan Lingfeng, Zhang Hong, Ma Zaiyong, Sun Wan, Pan Liangming, Deng Jiewen. Experimental Investigation on Void Fraction Distribution of Boiling Flow in 2×2 Rod Bundle Channel[J]. Nuclear Power Engineering, 2023, 44(6): 104-110. doi: 10.13832/j.jnpe.2023.06.0104

Citation:

Liu Hao, Zhang Luteng, Zhou Wenxiong, Zhu Longxiang, Wan Lingfeng, Zhang Hong, Ma Zaiyong, Sun Wan, Pan Liangming, Deng Jiewen. Experimental Investigation on Void Fraction Distribution of Boiling Flow in 2×2 Rod Bundle Channel[J]. Nuclear Power Engineering, 2023, 44(6): 104-110. doi: 10.13832/j.jnpe.2023.06.0104

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Experimental Investigation on Void Fraction Distribution of Boiling Flow in 2×2 Rod Bundle Channel

doi: 10.13832/j.jnpe.2023.06.0104

Liu Hao^{1, 2
,},
Zhang Luteng^{1, 2
,
,},
Zhou Wenxiong^{1, 2},
Zhu Longxiang^{1, 2},
Wan Lingfeng^{1, 2},
Zhang Hong^{1, 2},
Ma Zaiyong^{1, 2},
Sun Wan^{1, 2},
Pan Liangming^{1, 2},
Deng Jiewen^{1, 2}

1.
Key Laboratory of Low-grade Energy Utilization Technologies and Systems, Ministry of Education, Chongqing University, Chongqing, 400044, China
2.
Department of Nuclear Engineering and Technology, Chongqing University, Chongqing, 400044, China

Received Date: 2022-11-23
Rev Recd Date: 2023-05-06

Available Online: 2023-12-11

Publish Date: 2023-12-15

Abstract

Abstract

The conductivity probe method is an important methodology to obtain two-phase interfacial parameters. The radial distribution of the boiling flow void fraction in the 2 × 2 rod bundle channel was measured and analyzed by a one-sensor conductivity probe. The results show that under the current experimental conditions, from the fluctuation characteristics of the bubble signal, the fluctuation amplitude of the bubble signal main body at the center of the channel is small, and the fluctuation amplitude of the bubble signal main body at the rod gap is large. The radial distribution of void fraction shows the distribution characteristics of the core peak, and the core peak shows a concave phenomenon, which is due to the bubble at the center receives less heat than that at the wall.
- Conductivity probe,
- Rod bundle channel,
- Boiling flow,
- Void fraction

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References(32)

References

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