NUCLEAR TECHNIQUES, Volume. 48, Issue 7, 070031(2025)
Numerical simulation analysis and experimental validation for the reactor cavity of molten salt reactor
[20] Kim Hyun-Ju, Chi Se-Hwan, Kim Eung-Seon et al. Comparison of the thermal conductivity of selected nuclear graphite grades for high temperature gas-cooled reactor[C], 1-2.
[22] ZHAO Hangbin. Research and application of a multiscale coupled model for the reactor cavity cooling system of high temperature gas-cooled reactor[D](2018).
Get Citation
Copy Citation Text
Mudan MEI, Chong ZHOU, Yang ZOU, Yao FU, Naxiu WANG. Numerical simulation analysis and experimental validation for the reactor cavity of molten salt reactor[J]. NUCLEAR TECHNIQUES, 2025, 48(7): 070031
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: Nov. 8, 2024
Accepted: --
Published Online: Sep. 15, 2025
The Author Email: Chong ZHOU (ZHOUChong), Yang ZOU (ZOUYang), Yao FU (FUYao)