Автор туралы ақпарат

Porollo, S. I.

Шығарылым	Бөлім	Атауы	Файл
Том 120, № 3 (2016)	Article	Swelling and Radiation Creep of Ferrite-Martensite Steel Irradiated in the Bn-350 Reactor in a Wide Range of Temperature and Damaging Dose
Том 121, № 6 (2017)	Article	Analysis of Experimental Data on Gas Release and Swelling of Uranium Mononitride Fuel Irradiated in the BR-10 Reactor
Том 122, № 6 (2017)	Article	Experimental and Computational Investigation of the Emission of Radioactive Products from Irradiated Fuel of Fast Sodium-Cooled Reactor
Том 124, № 2 (2018)	Article	Study of the Long-Term Strength of Neutron-Irradiated Austenitic and Ferrite-Martensite Steel
Том 125, № 3 (2019)	Article	Corrosion Damage and Mechanical Properties of BR-10 Reactor Fuel-Rod Cladding with Mononitride Uranium Fuel
Том 125, № 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
Том 126, № 1 (2019)	Article	Study of Phase-Structural Transformations Resulting in Low-Temperature Radiation Embrittlement in Ferritic-Martensitic Steel
Том 126, № 3 (2019)	Article	Results of Studies of BN-600 Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel and ChS68-ID c.d. Steel Cladding