Experimental study of liquid sodium flow and heat transfer characteristics along a hexagonal 7-rod bundle

Author:

Hou Yandong,Wang Liu,Wang Mingjun,Zhang Kui,Zhang Xisi,Hu Wenjun,Wu Yingwei,Tian Wenxi,Qiu Suizheng,Su G.H.

Funder

China Institute of Atomic Energy

National Natural Science Foundation of China

Publisher

Elsevier BV

Subject

Industrial and Manufacturing Engineering,Energy Engineering and Power Technology

Reference28 articles.

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1. Numerical study on flow and heat transfer characteristics of liquid lithium in hexagonal rod bundle channels;Annals of Nuclear Energy;2024-12

2. Numerical study of the flow and heat transfer characteristics within the annular fuel element with double-sided cooling;Annals of Nuclear Energy;2024-05

3. Numerical study of turbulent heat transfer of annular fuel assembly in a sodium-cooled fast reactor by a SST k-ω-k θθ model;Journal of Nuclear Science and Technology;2024-02-12

4. References;Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors;2024

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