Design of a nuclear reactor core melt catcher on the basis of zirconia concrete.
#0101-2Ocean Nuclear Data Base (C)
Development of scientific and methodological basis for diagnostics and forecast of the state of Nuclear Waste at the bottom of the Barents and Kara Seas and the Sea of Japan. Identification of Ways to Prevent Dangerous Ecological Aftereffects.
Study on the Feasibility and Economics of the Use of Ex-Weapons Plutonium and Civil Plutonium as Fuel for both Fast and Thermal Reactors.
Design of Zircon-based Ceramics for a Nuclear Reactor Core Melt Catcher
Pilot Flow Lead-bismuth Target of MW Power for Accelerator-Driven Systems
Methodological Security of Temperature Measurement and Diagnostics within Power Water-moderated Water-cooled Reactor (PWR) Type on Base of Analysis of Influence Functions for Measuring Means.
Methodical Development for WWER-1000 Reactor Pressure Vessel Safe Operation Lifetime Evaluation Allowing for Anticorrosive Cladding
Design of a Catcher for the Molten Reactor Core at an NPP on the Basis of Zirconia Concrete
Creation of a Database for Computational Codes, Realizing Detailed Mathematical Modeling of a Radioactive Fission Products Realize from Fuel Rods VVER 440, VVER 1000
Verification of Thermal and Hydraulic Codes, Used for Safety Justification of Russian VVER NPPs
Study of Emergency Situations Related to Boron Dilution in WWER Reactors
Fuel Assembly Tests under Severe Accident Conditions
Scale Experimental Investigation of the Thermal and Structural Integrity of the VVER Pressure Vessel Lower Head in Severe Accident
Study of Fuel Assemblies under Severe Accident Top Quenching Conditions in the PARAMETER-SF Test Series
Modernization of Metrological Security of Reactor Thermometry Taking into Account Quality of Thermal Contact Between Thermocouple and Object and Degradation of its Characteristics at Irradiation
Study of Fuel Assemblies with Boron Carbide Absorber Rods under Severe Accident Conditions in the PARAMETER-SF Tests Series