Cite
Transient analysis of MOX-3600 and MET-1000 sodium-cooled fast reactor using SARAX code system.
MLA
Du, Xianan, et al. “Transient Analysis of MOX-3600 and MET-1000 Sodium-Cooled Fast Reactor Using SARAX Code System.” Annals of Nuclear Energy, vol. 121, Nov. 2018, pp. 324–34. EBSCOhost, https://doi.org/10.1016/j.anucene.2018.07.042.
APA
Du, X., Zheng, Y., Cao, L., & Wu, H. (2018). Transient analysis of MOX-3600 and MET-1000 sodium-cooled fast reactor using SARAX code system. Annals of Nuclear Energy, 121, 324–334. https://doi.org/10.1016/j.anucene.2018.07.042
Chicago
Du, Xianan, Youqi Zheng, Liangzhi Cao, and Hongchun Wu. 2018. “Transient Analysis of MOX-3600 and MET-1000 Sodium-Cooled Fast Reactor Using SARAX Code System.” Annals of Nuclear Energy 121 (November): 324–34. doi:10.1016/j.anucene.2018.07.042.