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.
Development of Scientific Fundamentals for Active Waste Minimization in Extraction Spent Nuclear Fuel (SNF) Reprocessing.
Process Development for Utilization of Civil and Military Plutonium in Fast and Thermal Reactors with Account for Ecology and Economics Requirements
Study on the Feasibility and Economics of the Use of Ex-Weapons Plutonium and Civil Plutonium as Fuel for both Fast and Thermal Reactors.
Conceptual Studies for Use of High-Enriched (Weapon Grade) Uranium and Plutonium and Power Plutonium under Conversion of Thermal Reactors to the Closed Uranium-Thorium Cycle
#0909-2Two-Cascade Power Blanket
Study of Neutron Multiplication in Media for Creating a Frequency Two-Cascade Energy Blanket
Development of Methods for Recovery of Palladium from Nitric Acid Solution Arising from NPR Fuel Reprocessing
Optimum Strategy for Nuclear Fuel Cycle Development in Russia
Completion of a Closed Tritium Circuit Device, Investigation of Processes, Manufacturing, and Tests of Models of ITER Tritium Loop Components; Experimental Simulation and Theoretical Analysis of Plasma Effects of ITER In-Vessel Structure Components; Radia
Investigation of the Radiation in Nuclear Fuel Cycle Based on Reprocessed Uranium and Mixed Uranium-Plutonium Fuel
Proton Induced Fission Cross Sections for Heavy Nuclei in the Energy Range 200-1000 MeV
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
Feasibility Study of the Blanket and Fusion Reactor Concept for Transmutation of Minor Actinides and Plutonium
Measurements of the Prompt Neutron Spectra of Minor Actinides. Fast Neutron Induced Fission of 241Am and 243Am, Thermal Neutron Induced Fission of 243Cm
Experimental and Theoretical Studies of the Yields of Residual Product Nuclei Produced in Thin Pb and Bi Targets Irradiated by 40–2600 MeV Protons
The Thermal-Hydraulic and Technological Investigations for Validation of the Project of Lithium Circulation Loop and Neutron Lithium Target for IFMIF
Foundation for Achievement of High Burn-up (20-30% HM) of Ceramic Fuel in LWR-type Reactors and for Upgrading the Fuel Proliferation Resistance
Experimental and Theoretical Study of the Residual Nuclide Production in 40-2600 MeV Proton-Irradiated Thin Targets of ADS Structure Materials
The International Science and Technology Center (ISTC) is an intergovernmental organization connecting scientists from Kazakhstan, Armenia, Tajikistan, Kyrgyzstan, and Georgia with their peers and research organizations in the EU, Japan, Republic of Korea, Norway and the United States.
ISTC facilitates international science projects and assists the global scientific and business community to source and engage with CIS and Georgian institutes that develop or possess an excellence of scientific know-how.