Experimental Study on the Impact of Heat Pipe Failure on High-Temperature Heat Pipe Bundles and Matrix

Wang Jinyuan; Li Panxiao; Wang Chenglong; Zhang Zeqin; Tian Wenxi; Qiu Suizheng; Su Guanghui

doi:10.13832/j.jnpe.2024.06.0254

Volume 45 Issue 6

Dec. 2024

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Article Navigation > Nuclear Power Engineering > 2024 > 45(6): 254-262

Wang Jinyuan, Li Panxiao, Wang Chenglong, Zhang Zeqin, Tian Wenxi, Qiu Suizheng, Su Guanghui. Experimental Study on the Impact of Heat Pipe Failure on High-Temperature Heat Pipe Bundles and Matrix[J]. Nuclear Power Engineering, 2024, 45(6): 254-262. doi: 10.13832/j.jnpe.2024.06.0254

Citation:

Wang Jinyuan, Li Panxiao, Wang Chenglong, Zhang Zeqin, Tian Wenxi, Qiu Suizheng, Su Guanghui. Experimental Study on the Impact of Heat Pipe Failure on High-Temperature Heat Pipe Bundles and Matrix[J]. Nuclear Power Engineering, 2024, 45(6): 254-262. doi: 10.13832/j.jnpe.2024.06.0254

Citation:

Wang Jinyuan, Li Panxiao, Wang Chenglong, Zhang Zeqin, Tian Wenxi, Qiu Suizheng, Su Guanghui. Experimental Study on the Impact of Heat Pipe Failure on High-Temperature Heat Pipe Bundles and Matrix[J]. Nuclear Power Engineering, 2024, 45(6): 254-262. doi: 10.13832/j.jnpe.2024.06.0254

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Experimental Study on the Impact of Heat Pipe Failure on High-Temperature Heat Pipe Bundles and Matrix

doi: 10.13832/j.jnpe.2024.06.0254

Nuclear Reactor Thermal Engineering and Hydraulics Laboratory, Xi’an Jiaotong University, Xi’an, 710049, China

Received Date: 2024-07-04
Rev Recd Date: 2024-08-29
Publish Date: 2024-12-17

Abstract

Abstract

In order to verify the feasibility of small heat pipe reactor, an experimental device of high temperature heat pipe bundle is designed in this study. The experimental device simulates the failure of heat pipe by pulling out the heat pipe, and simulates the core fuel rod by electric heating rod to explore the influence of heat pipe failure on heat pipe bundle, fuel rod and core matrix. It is found that the most direct impact of heat pipe failure is a sudden local temperature rise in the nearby matrix. Under the power of 4.2 kW, the average increase of matrix temperature in the vicinity of single heat pipe failure is about 70℃, and the average increase of matrix temperature in the vicinity of double heat pipe failure is about 120℃. The failure of a single heat pipe has a minor impact on the remaining normal heat pipes, with an average temperature rise of 15℃ in the evaporation section of the normal heat pipes. The average temperature increase of fuel element in the vicinity of double heat pipe failure is about 66℃. The experimental data of high temperature heat pipe bundle under heat pipe failure obtained in this study can provide data support for the modeling and simulation of heat pipe reactor.
- Heat pipe reactor,
- Heat pipe bundle,
- Heat pipe failure,
- Transient analysis

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References(9)

References

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