System design for safeguarding nuclear materials utilized at complex nuclear facilities.
Plasmachemical Technology Development with Processing Uranium Hexfluoride into Uranium Oxides for Long Storage and Fluorine Regeneration as Unaqueous Hydrogen Fluoride.
Determination of Radioactive Contamination of Weapons-grade Pu Production Reactors Graphite of Siberian Groups of Chemical Enterprises, SGCE, (Tomsk-7).
Development of Technology of Catalytic Fluidized Bed Destruction of Mixed Liquid Organic Wastes from Radiochemical and Chemical-Metallurgical Plants
Development of Fabrication Technology and Studies into the Properties of Fuel Materials Containing Skeleton-Type Inert Diluent (Without U-238) to Utilize Weapon Grade and Civil Pu as well as Minor Actinides (Np, Am, Cm, etc.) in Power Reactors With Improv
Development of a Nuclear Materials Control and Accounting System Model for Complex Nuclear Facilities
Analysis of Radioactive Contamination of the Graphite Sleeves Removed from the Plutonium Production Reactors of SGCE (Tomsk-7)
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
Mixed Oxide Fuel (MOX) -Born in Plasma
Determination of Radioactive Contamination and Conditions for Radioactive Wastes Storage in Interim Storage Ficilities (Vaults) of the Siberian Group of Chemical Enterprises (SGCE) for Substantiation of Measures for Safe Decommissioning of Plutonium-Produ
The Exploration of the Immobilization Method of Alpha-Active Wastes in Chemically Stable Porous Composites
Synthesis and Application of Nano-Sized Powders in Combustion Synthesis and Surface Engineering Technologies
The Development of a Method for Fixation and Compaction of Radioactive High-Level Waste in Combustion Mode
Development of methods and Hardware of Remote Control for Nuclear Reactors Conservation Technology and Other Technologies Applied in Nuclear-Hazardous Industry
Feasibility Study for the Development and Introduction of Radiation-Safe Technology for Handling Radioactive Graphite of Channel-Type Reactors
Study of Fluorine Composition from KF·2HF Electrolysis and Analysis Development for Concentration Determination of Fluorine Impurities by Multidimensional Gas Chromatography and Infrared Fourier Spectroscopy
Fire Retardand /Heat Resistant Paint, Primer Insulation and Other 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.