Studies of Fast Reactor Fuel Cycle to Burn Minor-Actinide.
Studies on Extraction of Fission Products from Fast Reactor Irradiated Fuel with Minor-Actinide Additives.
Complex Investigation of Uranium Dioxide and Mixed Uranium-Plutonium Dioxide Fuel's Properties for Prediction of Performance and Operating Characteristics and Verification of Calculating Models of Fuel elements for Operative and Advanced NPP.
#0534.2Uranium Dioxide Properties
Investigation Properties of Uranium Dioxide Advanced and Mixed Uranium-Plutonium fuels (MOX) for Prediction of Performance and Operating Characteristics to Provide Certification Fuel and Verification of Computational Models for Parameters Definition of Ox
Fundamental Research of Materials Structure and Properties Changes Resulted from Irradiation by Means of Complex of Modern Physical Methods
Development of the Long Term prediction Methods for Stress Rupture Strength (SRS) of Chloronium-nickel Austenitic steel on the basis of Shortcut Tests.
In-Pile Tests of New Generation Fuels for VVERs of Different Purpose
Study of Physico-chemical and Electrochemical Properties of the ADTT Fluoride Nuclear Fuel and Foundation of its Reprocessing
Multifunctional Computer Complex for Research Reactors
A Multipurpose Dynamic Electric System Simulator for the RIAR Power Complex
Experimental Study of Europium-152, 154, 155 Gamma-Sources, Obtained from Spent Control Rods of Transport, Power and Research Reactors
Development of Lithium Detector of Solar Neutrinos on a Basis of Prototype with 300 kgs of Lithium
Studying Features of Vibropack Oxide Fuel Pins Serviceability under the Limit Operational Parameters
System Analysis of Weapons and Civil Plutonium Utilization Scenarios in the Nuclear Fuel Cycle of Russia Taking into Account Economics, Non-Proliferation and Ecology Factors
Experimental and Theoretical Justification of the Cascade Scheme of the Subcritical Molten-Salt Reactor for Transmutation of Long-Lived RW of the Nuclear Fuel Cycle
Examination of VVER Fuel Behaviour under Severe Accident Conditions. Quench Stage. (SFD-VVER Project)
#1648.2Post-Crash Fuel Reflood
Examination of VVER Fuel Behavior under Severe Accident Conditions. Quench Stage
Investigation of Reactor Irradiation Effect on Radiation Stability and Mechanical Properties of Articles from Zirconium Alloys after High-Speed High-Frequency Treatment
Preparation of the Monograph "Boron in Nuclear Engineering"
Development of Scientific Fundamentals for Creation of Irradiation Resistant Structural Zr Alloys for Nuclear Reactor Cores
Processing Compact Weapon Plutonium into MOX-fuel by Anhydrous (Thermochemical and Thermoelectrochemical) Methods for Thermal and Fast Reactors
Development of the Tomographic Methods of Testing of the Fuel and its Components Distribution in Fuel Elements before and after Irradiation
Development of Treatment Methods, Technical Means and Small Sized Cf-252 Sources for Neutron Brachytherapy
MATINE - Study of Minor Actinide Transmutation in Nitrides: Modelling and Measurements of Out-of-pile Properties
Measurement of Transmutation Properties of Minor Actinides Irradiated in Intermediate Reactor Neutron Spectrum
Study of Curium Thermodynamics in Molten Chlorides
Fabrication of Experimental CANDU MOX Fuel Pins for Irradiation Testing in the MIR Reactor
Elaboration of Safe Methods for Radioactive Beryllium Waste Decontamination after Operation in a Nuclear Reactor
Preparation of the Monograph “Fuel Elements with Vibropacked Oxide Fuel”
MATINE 2- Study of Minor Actinide Transmutation in INErt Matrices Fuels: Modeling, Fabrication and Measurements of Out-of-Pile Properties
Fundamental Investigations of Processes, Responsible for Changes in Crystallographic Texture and Microstructure of Model Samples from Zr-Based Alloys under Neutron Irradiation
Investigation of Fission Products Release from Uranium Dioxide at Heat up Under Oxidizing and Reducing Media. VERONIKA Project.
Development of an Auger Spectroscopy Method for Measurement of Phosphorus Intergranular Segregations in PWR Reactor Pressure Vessel Steels
Examination of Radiation-Induced Damage in Candidate Materials of Neutron Multiplier for the Test Blanket Module of the International Thermonuclear Experimental Reactor (ITER)
Study of Curium Thermodynamics in Metallic Alloys
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