Mr
Joint Stock Company "Institute of Nuclear Materials"
Author in the following contributions
- Preliminary Inspection of Spent Fast Reactor Fuel Claddings
- Results of monitoring, using high-resolution neutron diffraction, of radiation-induced damages in claddings of fuel pins after their performance in the reactor BN-600 as a ground for prolongation of their life expectancy
- Modeling of Processes in Austenitic Steel Produced Under Irradiation in Fast Reactors and Possibilities of Model Practical Application
- Examination of Fast Reactor Materials and Structural Elements at JSC “INM” Premises
- FRACTURE STRAIN AND FRACTURE TOUGHNESS PREDICTION FOR IRRADIATED AUSTENITIC STEELS OVER WIDE RANGE OF TEMPERATURES TAKING INTO ACCOUNT THE EFFECT OF SWELLING AND THERMAL AGEING
- Examination of ChS-68 Steel Used as a BN-600 Reactor Cladding Material
- Change in Mechanical Properties of Spent Fast Reactor Claddings
- Investigation of Radiation-Induced Swelling of EK-164 Steel, an Advanced Material for BN-600 and BN-800 Claddings
