Creation of New Fuel Elements Generation for Water-Cooled Power Reactors of Different Purposes.
Automatic Television Analyzer Development for Industrial Microstructure Control of the Fuel Tablets (ATLANT-TT).
Investigation of the Radiation in Nuclear Fuel Cycle Based on Reprocessed Uranium and Mixed Uranium-Plutonium Fuel.
A Safe Method for Storing Large Masses of Plutonium and Uranium after Dismount of Nuclear Weapons.
#0332-2Safe U and Pu Storage
Project for the Safe Storage of large Masses of Weapon-grade Plutonium and Uranium
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.
Numerical Simulation of Nuclear Fuel Behavior under Accidents and Normal Operation
#0771MOX Fuel Fabrication
Development of Pulsed and Vibration Nuclear Power Reactor MOX Fuel Fabrication Equipment
#0967Gallium in MOX Fuel
Studies of the Influence of Ga Available in Weapons Grade Plutonium on the Quality of Produced Fuel and Serviceability of Fuel Rods
Development of Technology of ROX-Fuel Fabrication and Analysis of Characteristics of Nuclear Reactors Using ROX-Fuel
Studying Features of Vibropack Oxide Fuel Pins Serviceability under the Limit Operational Parameters
Development of Basic Principles of Processing of Plutonium in Fuel PuO2-x -Microspheres with Multi-layer Coating with the Purpose of a Disposition of a Weapons Plutonium with the Substantiation of Their Long-Duration and Safe Storage and/or Burn out in Nu
Development of Technology for Enriched Gd-157 Production Using Liquid Centrifuges
Development of a Fuel Element Diagnostics Technique for the Aperiodic Pulse Reactor BR-1 with the Metallic Core
Experimental and Theoretical Study of Thermophysical Properties of Uranium Dioxide (UO2) and Other Materials Related to the Problems of Nuclear Power Plants Safety
Microwave Technique of Uranium Hexafluoride Heating for Safe Evaporation from Containers, Including Damaged Ones
Study of Irregular Heterogeneous Effects in an LWR-Type Reactor Core
Investigation of HTGR Fuel Performance in WWR-K Research Reactor
#K-2222Investigation of HTGR fuel
Investigation of irradiated HTGR fuel properties
Conversion of the idle water discharges from reservoirs to the Hydrogen production by electrolysis and the thermolysis gas from hydrocarbons and coals
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.