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
توثيق أسلوب شيكاغو (الطبعة السابعة عشر)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, و 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.
توثيق جمعية اللغة المعاصرة MLA (الإصدار التاسع)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.