Accident Analysis of Heat Pipe Cooled Space Reactor System

Liu Songtao; Yuan Yuan; Wei Zonglan; Zeng Wei; Zhu Li; Gou Junli

doi:10.13832/j.jnpe.2016.05.0119

Volume 37 Issue 5

Feb. 2025

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Liu Songtao, Yuan Yuan, Wei Zonglan, Zeng Wei, Zhu Li, Gou Junli. Accident Analysis of Heat Pipe Cooled Space Reactor System[J]. Nuclear Power Engineering, 2016, 37(5): 119-124. doi: 10.13832/j.jnpe.2016.05.0119

Citation:

Liu Songtao, Yuan Yuan, Wei Zonglan, Zeng Wei, Zhu Li, Gou Junli. Accident Analysis of Heat Pipe Cooled Space Reactor System[J]. Nuclear Power Engineering, 2016, 37(5): 119-124. doi: 10.13832/j.jnpe.2016.05.0119

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Accident Analysis of Heat Pipe Cooled Space Reactor System

doi: 10.13832/j.jnpe.2016.05.0119

1. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610041 China;
2. School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, China

Received Date: 2016-07-03
Rev Recd Date: 2016-08-19

Available Online: 2025-02-15

Abstract

Abstract

A transient analysis code TAPIRS was developed to analyze the behavior of the heat pipe cooled space reactor power system based on the SAIRS models. Three typical accidents are analyzed using TAPIRS. The results show that the fuel temperature is below a safe limit under the control drum failure, the AMTEC failure and partial loss of the heat transfer area of radiator. This demonstrates that the reactor system is with the characteristics of self-stabilization ability under accident conditions.
- Space reactor,
- Heat pipe,
- AMTEC,
- Accident analysis