Author Details

Porollo, S. I.

Issue	Section	Title	File
Vol 120, No 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
Vol 121, No 6 (2017)	Article	Analysis of Experimental Data on Gas Release and Swelling of Uranium Mononitride Fuel Irradiated in the BR-10 Reactor
Vol 122, No 6 (2017)	Article	Experimental and Computational Investigation of the Emission of Radioactive Products from Irradiated Fuel of Fast Sodium-Cooled Reactor
Vol 124, No 2 (2018)	Article	Study of the Long-Term Strength of Neutron-Irradiated Austenitic and Ferrite-Martensite Steel
Vol 125, No 3 (2019)	Article	Corrosion Damage and Mechanical Properties of BR-10 Reactor Fuel-Rod Cladding with Mononitride Uranium Fuel
Vol 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
Vol 126, No 1 (2019)	Article	Study of Phase-Structural Transformations Resulting in Low-Temperature Radiation Embrittlement in Ferritic-Martensitic Steel
Vol 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