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#0173Fuel Elements for Water-Cooled Reactors

Creation of New Fuel Elements Generation for Water-Cooled Power Reactors of Different Purposes.

#0242TV Analyzer for Control of Fuel Pellets

Automatic Television Analyzer Development for Industrial Microstructure Control of the Fuel Tablets (ATLANT-TT).

#0273Radiation Characteristics of MOX Fuel

Investigation of the Radiation in Nuclear Fuel Cycle Based on Reprocessed Uranium and Mixed Uranium-Plutonium Fuel.

#0332Safe U and Pu Storage

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

#0534Uranium Dioxide Properties

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.

#0614Nuclear Fuel Behavior

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

#1321ROX-Fuel Fabrication

Development of Technology of ROX-Fuel Fabrication and Analysis of Characteristics of Nuclear Reactors Using ROX-Fuel

#1357Oxide Fuel Pins under Extreme Conditions

Studying Features of Vibropack Oxide Fuel Pins Serviceability under the Limit Operational Parameters

#1410Plutonium Oxide Microspheres

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

#1737Gd-157 Production Using Liquid Centrifuges

Development of Technology for Enriched Gd-157 Production Using Liquid Centrifuges

#2033Fuel Element Diagnostics for Pulse Reactor

Development of a Fuel Element Diagnostics Technique for the Aperiodic Pulse Reactor BR-1 with the Metallic Core

#2107Thermal Properties of Uranium Dioxide

Experimental and Theoretical Study of Thermophysical Properties of Uranium Dioxide (UO2) and Other Materials Related to the Problems of Nuclear Power Plants Safety

#2285Microwave Heating of Uranium Hexafluoride

Microwave Technique of Uranium Hexafluoride Heating for Safe Evaporation from Containers, Including Damaged Ones

#3814Irregular Heterogeneous Effects in a LWR Reactor

Study of Irregular Heterogeneous Effects in an LWR-Type Reactor Core

#K-1797Fuel for High Temperature Gas Cooled Reactor

Investigation of HTGR Fuel Performance in WWR-K Research Reactor

#K-2222Investigation of HTGR fuel

Investigation of irradiated HTGR fuel properties

#T-2109Hydrogen and Thermolysis gas production by use of energy of idle water flow

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.

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