Numerical and experimental analysis of LBE flow and heat transfer characteristics in hexagonal rod bundles

Author:

Zhou XingguangORCID,Zhang DalinORCID,Liu Jie,Lin Chao,Liang Yu,Tian Wenxi,Qiu Suizheng,Su Guanghui

Funder

China National Nuclear Corporation

National Natural Science Foundation of China

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference44 articles.

1. European lead fast reactor—ELSY;Alemberti;Nucl. Eng. Des.,2011

2. Lead-cooled fast reactor systems and the fuels and materials challenges;Allen;Science & Technology of Nuclear Installations,2007

3. ANSALDO, 2010. Lead-cooled European Advanced Demonstration Reactor (LEADER) – Annex I “Description of Work”, Grant Agreement No. FP7-249668, Rev. 0.

4. ANSYS Fluent, 2019. ANSYS Help 2019 R3. ANSYS.

5. CFD analysis of flow blockage phenomena in a LBE-cooled 19-pin wire-wrapped rod bundle;Chai;Nucl. Eng. Des.,2019

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