Research and test facility
- Thermo-hydraulic Test Facility-model of Water-cooled Reactors (PSB-VVER)
- Thermo-hydraulic Test Facility-model of Water-cooled Reactors (ISB-VVER)
- Test Facility-model of the Secondary Circuit of NPP with VVER-1000 reactor type (V-3)
- Full-scale Test Facility of safety of RBMK reactor (PSB-RBMK)
- Group of Test facilities for studying Thermo–mechanical Problems of the RBMK Core (TKR, TKR–F)
- Test-Facility model of the Bubble–condenser Accident Localization System at NPP with VVER–440/213 (BC V–213)
- Chemical-engineering Test Facility for testing the ion-resins on osmotic stability and mechanical strength in dynamic conditions (OSMOS)
- Calibration flow-measuring rig UPR-50
- Test Facility for testing of heat exchanging equipment
- Test Facility for Pump-Ejector Set tests
- Test Facilities for studying of average and local velocities in cells of fuel assembly models (LIS Test facility)
- APCS of NPP
- Automation of Non–standard Objects and Systems
- Test Facility for washing of technological equipment
- Test Facility for research of erosion and corrosion wear (MPK)
- Development of the Codes for NPP's Thermal-Hydraulic Processes
- New generation Codes
- «Ecological, technological and nuclear safety of the enterprises used nuclear materials, sources of the ionizing radiation, radioactive substances and radioactive waste». The database
- Steam flow measuring system
- Technical Proposals on Enhancement of Efficiency of Heat–and–power Engineering Equipment Operation
- Developing of Water Chemistry Control and Managing System for VVER
- The program on enhancement of operation quality, tests procedures and turbine and transformer oils quality control at NPP
- Resource–saving Equipment Designing