Cite
Development of a thermal–hydraulic analysis code for the Pebble Bed Water-cooled Reactor
MLA
Cai, Xiaoyu, et al. “Development of a Thermal–hydraulic Analysis Code for the Pebble Bed Water-Cooled Reactor.” Nuclear Engineering & Design, vol. 241, no. 12, Dec. 2011, pp. 4978–88. EBSCOhost, https://doi.org/10.1016/j.nucengdes.2011.09.007.
APA
Cai, X., Qiu, S., Tian, W., & Su, G. (2011). Development of a thermal–hydraulic analysis code for the Pebble Bed Water-cooled Reactor. Nuclear Engineering & Design, 241(12), 4978–4988. https://doi.org/10.1016/j.nucengdes.2011.09.007
Chicago
Cai, Xiaoyu, Suizheng Qiu, Wenxi Tian, and Guanghui Su. 2011. “Development of a Thermal–hydraulic Analysis Code for the Pebble Bed Water-Cooled Reactor.” Nuclear Engineering & Design 241 (12): 4978–88. doi:10.1016/j.nucengdes.2011.09.007.