M. A. Konovalov

TL;DR: In this article, the authors show that in principle it is possible by relying on the BN-600 design to secure the required parameters of a reactor setup with a fast reactor with high-temperature sodium coolant (BN-VT) for hydrogen production.

TL;DR: Retrospective analysis of coolant purification systems in nuclear reactors from BR-5 to BN-1200, such as cold traps and sorbents for purification from cesium ensuring successful operation of nuclear power installations equipped with sodium-cooled fast neutron reactors and hot traps representing promising concept to be used for sodium purifying from oxygen on NPPs demonstrated that there exist capabilities for enhancing characteristics of such systems.

TL;DR: In this article, it was proposed to use hot traps (HTs) in circuit I for coolant purification from oxygen, and it was demonstrated that the efficiency of purification systems can be increased using HTs with the getter in the form of a foil or granules.

TL;DR: In this article, a diffusion model was used to evaluate the effect of cesium ingress into sodium through the sealed fuel rod cladding in high-temperature nuclear power installations (HT NPIs).

TL;DR: In this article, the authors proposed a BN-VT reactor with 600MW thermal power and demonstrated the possibility in principle to achieve the required parameters of high-temperature fast reactor for production of large quantities of hydrogen on the basis, for instance, of one of thermal chemical cycles or high temperature hydrolysis with high thermal efficiency of use of electric power.