Mr
Institute of Nuclear Materials
Author in the following contributions
- Examination of Fast Reactor Materials and Structural Elements at JSC “INM” Premises
- POSTREACTOR STATE OF THE STANDARD AND EXPERIMENTAL BN-600 FUEL KINDS
- Change in Mechanical Properties of Spent Fast Reactor Claddings
- STATISTICAL INVESTIGATION OF RADIATION-INDUCED POROSITY IN BN FUEL CLADDINGS USING SCANNING ELECTRON MICROSCOPY
- Thermal Annealing Effect on Recovery of Corrosion Properties of EP-450 Steel Irradiated IN BN-600 Reactor to High Damage Doses