Experimental Research on the Flow Characteristics in the Top Cover Plenum and the Upper Plenum of Pressurized Water Reactor

Li Kaidi; Wang Kuo; Wang Long; Xie Chong; Du Bing

doi:10.13832/j.jnpe.2024.11.0104

Volume 46 Issue 4

Aug. 2025

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Li Kaidi, Wang Kuo, Wang Long, Xie Chong, Du Bing. Experimental Research on the Flow Characteristics in the Top Cover Plenum and the Upper Plenum of Pressurized Water Reactor[J]. Nuclear Power Engineering, 2025, 46(4): 109-116. doi: 10.13832/j.jnpe.2024.11.0104

Citation:

Li Kaidi, Wang Kuo, Wang Long, Xie Chong, Du Bing. Experimental Research on the Flow Characteristics in the Top Cover Plenum and the Upper Plenum of Pressurized Water Reactor[J]. Nuclear Power Engineering, 2025, 46(4): 109-116. doi: 10.13832/j.jnpe.2024.11.0104

Citation:

Li Kaidi, Wang Kuo, Wang Long, Xie Chong, Du Bing. Experimental Research on the Flow Characteristics in the Top Cover Plenum and the Upper Plenum of Pressurized Water Reactor[J]. Nuclear Power Engineering, 2025, 46(4): 109-116. doi: 10.13832/j.jnpe.2024.11.0104

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Experimental Research on the Flow Characteristics in the Top Cover Plenum and the Upper Plenum of Pressurized Water Reactor

doi: 10.13832/j.jnpe.2024.11.0104

Comprehensive Thermal-Hydraulic and Safety Laboratory (Guangdong Provincial Key Laboratory of Nuclear Power Safety), China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen, Guangdong, 518116, China

Received Date: 2024-10-31
Accepted Date: 2024-12-18
Rev Recd Date: 2024-12-16
Publish Date: 2025-08-15

Abstract

Abstract

In order to obtain the flow characteristics in the top cover plenum and the upper plenum of an advanced pressurized water reactor, the flow field distribution characteristics of typical areas in the top cover plenum were studied by the particle image velocimetry (PIV) technique, and transverse hydraulic loads on the control rod guide tube assemblies (CRGT) and the support column assemblies near the outlet of the upper plenum were also measured by self-developed force sensors, under different mainstream flow conditions on a 1∶5 scaled experimental model. The results show that intense whirlpools were found near the central thermal sleeve bell mouth under uniform and non-uniform flow conditions, which may lead to stronger impact and abrasion on central thermal sleeves; loads on CRGTs are generally higher than those on support column assemblies, load directions of measuring points are basically consistent with flow directions of coolant, and the load is negatively correlated with the distance from the measuring point to the outlet of the upper plenum; the flow characteristics of coolant under non-uniform flow condition are basically consistent with those under uniform flow condition, which verifies the conservative safety of the reactor design. Therefore, this study is of great significance for structural mechanics analysis, abrasion mechanism analysis, flow-induced vibration evaluation and falling rod performance analysis.
- Pressurized water reactor,
- Top cover plenum,
- Upper plenum,
- Flow field,
- Transverse hydraulic load

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References(26)

References

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