Transient analyses on loss of heat sink and overpower transient of natural circulation LBE-cooled fast reactor

Gu, Zhixing; Wang, Gang; Wang, Zhen; Jin, Ming; Wu, Yican

doi:10.1016/j.pnucene.2015.01.010

Cited by 12 publications

References 17 publications

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Study on the 3-D Natural Circulation Characteristics of LFR Under Steady State by Using Ansys Fluent

Dai

Yan

et al. 2023

Springer Proceedings in Physics

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As one of the Generation IV reactors, Lead-based Fast Reactor (LFR) has been considered to be great promising owing to its advantages in nuclear safety, sustainable development of nuclear energy and nuclear waste disposal. Owing to the excellent thermal expansion characteristics of Lead-based coolant materials, the primary cooling system of LFR can operate in natural circulation driven mode. The CFD (Computational Fluid Dynamics)-based thermal-hydraulics and safety analyses of nuclear reactors, especially liquid metal pool-type reactors have attracted great attentions in recent years. In this paper, the entire 3-D geometric model of a 10 MWth natural circulation driven LFR primary cooling system was established and simulated by ANSYS Fluent, in which the mesh was partitioned by utilizing structured meshing technology, and the porous medium model was utilized to fine the reactor core simulation. The results showed that the above LFR can operate safely in natural circulation mode, and has excellent natural circulation characteristics for the primary cooling system.

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