APA (7th ed.) Citation

Bedenko S. V. Sergey Vladimirovich, Lutsik I. O. Igor Olegovich, Prikhodko V. V. Vadim Vadimovich, Matyushin A. A. Anton Andreevich, Polozkov S. D. Sergey Dmitrievich, Shmakov V, M. V. M., . . . Vega-Carrillo H. R. Hector Rene. (2023). Neutronic and thermohydraulic blanket analysis for hybrid fusion–fission reactor during operation; Nuclear Engineering and Technology; Vol. 55, iss. 7. 2023. https://doi.org/10.1016/j.net.2023.03.032

Chicago Style (17th ed.) Citation

Bedenko S. V. Sergey Vladimirovich, Lutsik I. O. Igor Olegovich, Prikhodko V. V. Vadim Vadimovich, Matyushin A. A. Anton Andreevich, Polozkov S. D. Sergey Dmitrievich, M. Vladimir Mikhaylovich Shmakov V, Modestov D. G. Dmitry Gennadjevich, and Vega-Carrillo H. R. Hector Rene. Neutronic and Thermohydraulic Blanket Analysis for Hybrid Fusion–fission Reactor During Operation; Nuclear Engineering and Technology; Vol. 55, Iss. 7. 2023, 2023. https://doi.org/10.1016/j.net.2023.03.032.

MLA (9th ed.) Citation

Bedenko S. V. Sergey Vladimirovich, et al. Neutronic and Thermohydraulic Blanket Analysis for Hybrid Fusion–fission Reactor During Operation; Nuclear Engineering and Technology; Vol. 55, Iss. 7. 2023, 2023. https://doi.org/10.1016/j.net.2023.03.032.