A Study on Safety Analysis of Heat Pipe Cooled Reactor Based on Unmanned Underwater Vehicle

Xu Shihao; Gou Junli; Shan Jianqiang; Ouyang Zeyu; Wang Zheng

doi:10.13832/j.jnpe.2023.S1.0021

Volume 44 Issue S1

Jun. 2023

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Xu Shihao, Gou Junli, Shan Jianqiang, Ouyang Zeyu, Wang Zheng. A Study on Safety Analysis of Heat Pipe Cooled Reactor Based on Unmanned Underwater Vehicle[J]. Nuclear Power Engineering, 2023, 44(S1): 21-28. doi: 10.13832/j.jnpe.2023.S1.0021

Citation:

Xu Shihao, Gou Junli, Shan Jianqiang, Ouyang Zeyu, Wang Zheng. A Study on Safety Analysis of Heat Pipe Cooled Reactor Based on Unmanned Underwater Vehicle[J]. Nuclear Power Engineering, 2023, 44(S1): 21-28. doi: 10.13832/j.jnpe.2023.S1.0021

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A Study on Safety Analysis of Heat Pipe Cooled Reactor Based on Unmanned Underwater Vehicle

doi: 10.13832/j.jnpe.2023.S1.0021

School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, 710049, China

Received Date: 2023-02-21
Rev Recd Date: 2023-05-10
Publish Date: 2023-06-15

Abstract

Abstract

Based on a compact heat pipe-cooled reactor carried by an unmanned underwater vehicle, a complete safety analysis model of heat pipe cooled reactor is established and optimized in this paper, which mainly includes core power transient model, cold start-up model of high temperature heat pipe and two-dimensional heat pipe grid model. The passive residual heat removal system under accident condition is also designed. A heat pipe-cooled reactor safety analysis program was developed based on the established model, and the program's calculated results were compared and verified with published experimental data of cold start-up and stable operation. The verification results showed good agreement between the program's calculated results and experimental data, demonstrating the accuracy of the program and the reliability of the predicted results. The typical accident of the research object was analyzed by using the program, and the highest temperature was calculated to be 1085K under the heat sink loss accident condition, with a delay of reactor shutdown for 3s and a delay in putting residual heat removal system into operation for 6s, and it's below the maximum operating temperature of the heat pipe. The transient response of the reactor temperature with a step-in positive reactivity insertion of 0.47$ and a linear reactivity insertion of ±0.05$ was also calculated, and the highest temperature was below the maximum operating temperature of the heat pipe. Under feedback regulation, the reactor reached a new steady state at a higher power level, demonstrating the good inherent safety of the reactor design scheme.
- Heat pipe cooled reactor,
- Safety analysis program,
- Program verification,
- Accident analysis

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References(15)

References

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