Abstract

.A lead-based reactor with employing heat pipes as passive residual heat removal system (PRHRS) for longterm decay heat removal was designed. Three-dimensional computational fluid dynamics (CFD) software FLUENT was adopted to simulate the thermal-hydraulic characteristics of the PRHRS under Station-Black-Out (SBO) accident condition. The results showed that heat in the core could be removed smoothly by the PRHRS, and the core temperature difference is less than 20 K.

Highlights

  • Razzaque proposed to adopt heat pipes as the passive residual heat removal system (PRHRS) for liquid metal cooled reactors and evaluated the impact of different cooling environment on the heat pipe system

  • Wang et al simulated the start-up process of sodium heat pipes, which were used as the PRHRS of the reactor[2]

  • The existence of the heat pipe leads to the local temperature imbalance and forms the local natural circulation of fluid, which promote the heat release from the reactor core

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Summary

Introduction

Razzaque proposed to adopt heat pipes as the PRHRS for liquid metal cooled reactors and evaluated the impact of different cooling environment on the heat pipe system. The results showed that the heat pipes have good heat transfer performance. The results showed that heat pipes are able to reduce the reactor temperature from the operation temperature 282 oC to below 250 oC within 7 h. Qin et al proposed a method to directly insert the heat pipes into the containment for long-term residual heat removal and studied the influence of different operation conditions on the process parameters of the system by experiments[4]. The results showed the heat transfer efficiency was significantly improved, and the heat pipes could effectively reduce the heat accumulation in the containment and delay the temperature increase of the water coolant in the containment. The temperature characteristics of the heat pipe reactor were studied by using FLUENT.

Reactor design description
The geometry model of the LBE reactor
The PHX model
The reactor core model
Thermal validation of the LBE reactor numerical model
Results and discussions
Conclusion
Full Text
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