Cite
Development of fuel rod behavior analysis code and its application to supercritical CO2 cooled nuclear reactor.
MLA
Zhang, K., et al. “Development of Fuel Rod Behavior Analysis Code and Its Application to Supercritical CO2 Cooled Nuclear Reactor.” Annals of Nuclear Energy, vol. 164, Dec. 2021, p. N.PAG. EBSCOhost, https://doi.org/10.1016/j.anucene.2021.108618.
APA
Zhang, K., Yang, T. A., Liao, H. Y., Xie, X. F., Chen, R. H., Tian, W. X., Su, G. H., & Qiu, S. Z. (2021). Development of fuel rod behavior analysis code and its application to supercritical CO2 cooled nuclear reactor. Annals of Nuclear Energy, 164, N.PAG. https://doi.org/10.1016/j.anucene.2021.108618
Chicago
Zhang, K., T.A. Yang, H.Y. Liao, X.F. Xie, R.H. Chen, W.X. Tian, G.H. Su, and S.Z. Qiu. 2021. “Development of Fuel Rod Behavior Analysis Code and Its Application to Supercritical CO2 Cooled Nuclear Reactor.” Annals of Nuclear Energy 164 (December): N.PAG. doi:10.1016/j.anucene.2021.108618.