NUCLEAR TECHNIQUES, Volume. 48, Issue 7, 070019(2025)
Numerical simulation of thermal stratification characteristics in the upper plenum chamber of lead-based fast reactors
[17] Yoshikawa S, Minami M. Data description for coordinated research project on benchmark analyses of sodium natural convection in the upper plenum of the MONJU reactor vessel under supervisory of technical working group on fast reactors, International Atomic Energy Agency[R](2009).
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Yue WANG, Xuanming LIU, Fengchen LI, Hongna ZHANG, Shuqi MENG, Xin WANG, Yulong MAO, Qian LI, Weihua CAI. Numerical simulation of thermal stratification characteristics in the upper plenum chamber of lead-based fast reactors[J]. NUCLEAR TECHNIQUES, 2025, 48(7): 070019
Category: Special Issue on The First Academic Annual Conference of the Research Reactor and Innovative Reactor Association of Chinese Nuclear Society and Advanced Nuclear Power System Reactor Engineering
Received: Dec. 24, 2024
Accepted: --
Published Online: Sep. 15, 2025
The Author Email: Weihua CAI (CAIWeihua)