Neutronic and thermohydraulic blanket analysis for hybrid fusion–fission reactor during operation

Autor: Bedenko, Sergey V., Lutsik, Igor O., Prikhodko, Vadim V., Matyushin, Anton A., Polozkov, Sergey D., Shmakov, Vladimir M., Modestov, Dmitry G., Vega–Carrillo, Hector Rene
Zdroj: In Nuclear Engineering and Technology July 2023 55(7):2678-2686
Databáze: ScienceDirect