A review on thermohydraulic and mechanical-physical properties of SiC, FeCrAl and Ti3SiC2 for ATF cladding
2019 · Nuclear Engineering and Technology · 107 citations
https://doi.org/10.1016/j.net.2019.07.030
M
Mingjun Wang
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Mingjun Wang is an academic researcher from Chongqing University of Posts and Telecommunications. The author has contributed to research in topics: Nuclear Engineering Thermal-Hydraulics & Nuclear reactor physics and engineering & Nuclear Materials and Properties. The author has an h-index of 37, co-authored 266 publications.
ORCID: 0000-0003-0476-3294Papers by this author
worksNumerical simulation of three-dimensional flow and heat transfer characteristics of liquid lead–bismuth
2020 · Nuclear Engineering and Technology · 51 citations
https://doi.org/10.1016/j.net.2020.12.025
Best estimate plus uncertainty analysis of the China advanced large-scale PWR during LBLOCA scenarios
2020 · International Journal of Advanced Nuclear Reactor Design and Technology · 20 citations
https://doi.org/10.1016/j.jandt.2020.07.002
Hybrid medium model for conjugate heat transfer modeling in the core of sodium-cooled fast reactor
2019 · Nuclear Engineering and Technology · 14 citations
https://doi.org/10.1016/j.net.2019.09.009
Study on three-dimensional numerical simulation of shell and tube heat exchanger of the surface ship under marine conditions
2022 · Nuclear Engineering and Technology · 13 citations
https://doi.org/10.1016/j.net.2022.12.020
Microstructure and interface-adhesion of thermally sprayed continuous gradient elastic modulus FeCrAl-ceramic coatings
2019 · Ceramics International · 11 citations
https://doi.org/10.1016/j.ceramint.2019.11.048
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