Cite

Code development and safety analyses for Pb–Bi-cooled direct contact boiling water fast reactor (PBWFR).

MLA

Tian, Y. H., et al. “Code Development and Safety Analyses for Pb–Bi-Cooled Direct Contact Boiling Water Fast Reactor (PBWFR).” Progress in Nuclear Energy, vol. 68, Sept. 2013, pp. 177–87. EBSCOhost, https://doi.org/10.1016/j.pnucene.2013.07.003.



APA

Tian, Y. H., Su, G. H., Wang, J., Tian, W. X., & Qiu, S. Z. (2013). Code development and safety analyses for Pb–Bi-cooled direct contact boiling water fast reactor (PBWFR). Progress in Nuclear Energy, 68, 177–187. https://doi.org/10.1016/j.pnucene.2013.07.003



Chicago

Tian, Y.H., G.H. Su, J. Wang, W.X. Tian, and S.Z. Qiu. 2013. “Code Development and Safety Analyses for Pb–Bi-Cooled Direct Contact Boiling Water Fast Reactor (PBWFR).” Progress in Nuclear Energy 68 (September): 177–87. doi:10.1016/j.pnucene.2013.07.003.