Cite
The oxidation of alloy 690 in simulated pressurized water reactor primary water.
MLA
Kuang, Wenjun, et al. “The Oxidation of Alloy 690 in Simulated Pressurized Water Reactor Primary Water.” Corrosion Science, vol. 126, Sept. 2017, pp. 227–37. EBSCOhost, https://doi.org/10.1016/j.corsci.2017.07.004.
APA
Kuang, W., Song, M., Wang, P., & Was, G. S. (2017). The oxidation of alloy 690 in simulated pressurized water reactor primary water. Corrosion Science, 126, 227–237. https://doi.org/10.1016/j.corsci.2017.07.004
Chicago
Kuang, Wenjun, Miao Song, Peng Wang, and Gary S. Was. 2017. “The Oxidation of Alloy 690 in Simulated Pressurized Water Reactor Primary Water.” Corrosion Science 126 (September): 227–37. doi:10.1016/j.corsci.2017.07.004.