Cite
The development of nuclear reactor three-dimensional neutronic thermal–hydraulic coupling code: CorTAF-2.0.
MLA
Dong, Zhengyang, et al. “The Development of Nuclear Reactor Three-Dimensional Neutronic Thermal–hydraulic Coupling Code: CorTAF-2.0.” Nuclear Engineering & Design, vol. 415, Dec. 2023, p. N.PAG. EBSCOhost, https://doi.org/10.1016/j.nucengdes.2023.112689.
APA
Dong, Z., Liu, K., Wang, M., Tian, W., Qiu, S., & Su, G. H. (2023). The development of nuclear reactor three-dimensional neutronic thermal–hydraulic coupling code: CorTAF-2.0. Nuclear Engineering & Design, 415, N.PAG. https://doi.org/10.1016/j.nucengdes.2023.112689
Chicago
Dong, Zhengyang, Kai Liu, Mingjun Wang, Wenxi Tian, Suizheng Qiu, and G.H. Su. 2023. “The Development of Nuclear Reactor Three-Dimensional Neutronic Thermal–hydraulic Coupling Code: CorTAF-2.0.” Nuclear Engineering & Design 415 (December): N.PAG. doi:10.1016/j.nucengdes.2023.112689.