Mr
Institute of Nuclear Materials
Author in the following contributions
- Preliminary Inspection of Spent Fast Reactor Fuel Claddings
- Examination of Fast Reactor Materials and Structural Elements at JSC “INM” Premises
- POSTREACTOR STATE OF THE STANDARD AND EXPERIMENTAL BN-600 FUEL KINDS
- Investigation of Radiation-Induced Swelling of EK-164 Steel, an Advanced Material for BN-600 and BN-800 Claddings