Informaçao sobre o Autor

Nikitin, O. N.

Edição	Seção	Título	Arquivo
Volume 122, Nº 3 (2017)	Article	Investigations of Mixed Uranium-Plutonium Nitride Fuel in Project Breakthrough
Volume 122, Nº 5 (2017)	Article	Particulars of Uranium-Plutonium Nitride Fuel Swelling During Low-Temperature Irradiation in Fast Reactor to Burnup 5.5% h.a.
Volume 125, Nº 5 (2019)	Article	Results of Investigations of BREST-Type Reactor Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel, Irradiated in BOR-60 and BN-600
Volume 126, Nº 3 (2019)	Article	Results of Studies of BN-600 Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel and ChS68-ID c.d. Steel Cladding