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Publications by V.А. Kurnaev
Fusion Hybrid With Thorium Blanket: On Its Innovative Potential in Fuel Cycle of Nuclear Reactors
Problems of Atomic Science and Technology, Series Thermonuclear Fusion
High Energy Physics
Nuclear
Engineering
Nuclear Energy
Condensed Matter Physics
Related publications
On-Site Nuclear Fuel Cycle of “BREST” Reactors
International Journal of Energy and Power Engineering
Tritium Breeding Potential and Requirements for D-T Fuel Cycle in Fusion Reactors.
Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan
Non-Proliferative, Thorium-Based, Core and Fuel Cycle for Pressurized Water Reactors
Modular Fission--Fusion Hybrid Blanket
Cost of Processing Fuel From a Molten Salt, Fusion-Fission, Hybrid Reactor Blanket
The International Journal of Applied Radiation and Isotopes
Nuclear Analysis on the Enrichment of PWR Fuel in a Fusion Hybrid Reactor
Fusion Fuel Cycle: Material Requirements and Potential Effluents
Current Status and Future Direction of INPRO (International Project on Innovative Nuclear Reactors and Fuel Cycles)
Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan
Potential Advantages of Fusion Power Reactors
IEEE Transactions on Nuclear Science
Electronic Engineering
Nuclear
Nuclear Energy
High Energy Physics
Engineering
Electrical
