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

This work demonstrates the results of full-scale numerical experiments of a hybrid thorium-containing fuel plant operating in a state close to critical due to a controlled source of D–T neutrons. The proposed facility represented a level of generated power (∼10–100 MWt) in a small pilot. In this wor...

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Hlavní autoři:	Sergey V. Bedenko, Igor O. Lutsik, Vadim V. Prikhodko, Anton A. Matyushin, Sergey D. Polozkov, Vladimir M. Shmakov, Dmitry G. Modestov, Hector Rene Vega–Carrillo
Médium:	Artigo
Jazyk:	Inglês
Vydáno:	Elsevier 2023-07-01
Edice:	Nuclear Engineering and Technology
Témata:	Hybrid fusion–fission reactor facility Thorium D–T neutrons Neutronic and thermohydraulic studies
On-line přístup:	http://www.sciencedirect.com/science/article/pii/S1738573323001419
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