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#1922Nanocrystalline Alloys with Enhanced Properties

The Creation of Scientific Basis for Development of Technology for Manufacturing Sheets and Strips of Fe- and Cu-based Alloys with Nanocrystalline Structure with Enhanced Strength, Electric Conductivity and Damping Properties

#K-012Safety Issues of VVR-K

Studies of Safety Issues of VVR-K Reactor Facility under Enhanced Seismic Activity and in View of its Future Use.

#K-041Image Determination Space Nuclear Power System Reactor

Image Determination Space Nuclear Power System Reactor Generating Electricity and Laser radiation with International Safety Properties.

#K-056Simulation of Semipalatinsk Waste Transport

Simulation of Contaminant Transport in Underground Water at Semipalatinsk Nuclear Test Site.

#K-061Heavy Oil Products Regeneration

Technology of Heavy Oil Residue and Used Foul Oil Stuff Regeneration and Refining.

#K-073Biological Objects at Semipalatinsk Site

ESR-Dosimetry of Biological Objects from Semipalatinsk Nuclear Test Site

#K-172Reactor Structural Material Degradation

Study of Structural Materials of the Nuclear Reactor WWR-K in View of its Recommissioning

#K-226Radionuclides Migration Prevention

Prevention of Radionuclide Migration from the Soil of Semipalatinsk Nuclear Test Site by Using of Interpolymer Complexes

#K-274Gaseous Reactor Fuel Channel

Researches on the Substantiation of Possibility of Creation of Gaseous Fuel Channel of an Active Zone of Nuclear Reactor with Circulating Nuclear Fuel-Hexafluoride of Uranium (UF6)

#K-512Cesium Trap for BN-350 Reactor

Develop, Install, and Operate a Cesium Trap, Based on the U.S. Technologies, to Reduce Cesium Levels in the BN-350 Primary Sodium and Enhance Plant Fire Protection Capabilities to Support Cesium Trap Operation

#K-559Decontamination of Undeground Nuclear Cavity Solutes

Developing the Methods of Radioactive Decontamination of Underground Nuclear Cavity Aqueous Solutes in Salt Rock

#K-812Fuel Assembly Materials under Dry Storage

Behavior of Nuclear Reactor Fuel Assembly Materials during Their Long-Term Dry Storage

#K-812.2Fuel Assembly Materials under Dry Storage

Behavior of Nuclear Reactor Fuel Assembly Materials during Their Long-Term Dry Storage

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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