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Thermo-hydraulic Test facility-models of Water-moderated Reactors (PSB-VVER and ISB-VVER)
Chemistry-engineering Test facility-model of the Secondary Curcuit of NPP with Water-moderated Reactor (V-3)
Thermo-hydraulic Test facility-model of the Channel-type Reactor (PSB-RBMK)
Group of Test facilitys for Investigation of Thermo–mechanical Problems of the RBMK Core (TKR, TKR-F and TKR-M)
Testbed–model of the Bubble–condenser Accident Localization System at NPP with VVER–440/213 (BC V–213)
Chemical-engineering Test Facility for Testing Ion-exchange Resins for Osmotic Stability and Mechanical Strength in Dynamic Conditions (ION-1)
Hydrodynamic Channel (Vitra)
The Test Facility for Investigation of Effectiveness of the Antidebris Filters of the Fuel Assemblies of the Power Water Cooled Reactors
(Filter-1)
The Test Facility for Investigation of Thermo-hydraulic Characteristics of the Water Cooled Power Installation Components (DNK)
Calibration Flowmeasuring Rig UPR–50
Experimental Heat–exchange Facility
Web–based Database «EREC-STRESA»
Development of Calculation Codes for Analysis of NPP Thermohydraulic Processes
APCS Testing Site
Automation of Non–standard Objects and Systems