Development of Reactor Lifetime Precise Calculation Code on Base of Monte-Carlo Method.
Investigation of Promising Fuel Materials for PWR Having Maneuverable Operating Conditions.
Hybrid Reactor (TEC-NIT) Conceptual Design Development
Development of Technology of Production of Some Temperature and Radiation Resistant sic-based Semiconductor Structures
Investigation of non-thermal Possibilities of Origin of the Superconductivity in High-Energy Pulsed High-gamma-neutron Fluxed.
Development and Computational-Experimental Validation of the Concept of Self-Quenching Multi-channel Pulse Graphite Reactor (MIGR) for the Studies on Nuclear Reactor Safety.
Development of Plants for the Production of Highly Concentrated Boron Isotopes and Synthesis of Boric Acid Labeled with Boron-10 and Boron-11 Isotopes; Development of the Process for the Production of Highly Pure Elementary Boron.
Development of Methods and Creation of the Equipment Complex for Thermonuclear Plasma Diagnostics at Tokamak by Neutrons and Charged Fusion Products.
Theoretical Fundamentals for Multicomponent Isotope Separation by a Gas Centrifuge.
The Development of AgCl Crystals Growth Technology and the Creating of Infrared Range Optical Elements for Cryogenic Spectroscopy and Isotopes Separation.
Analysis of Accident Evolution and Consequences for the 4th Block Chernobyl Nuclear Power Plant.
Radioecological Consequences of Contamination of the Lakes after the Chernobyl Accident and Analysis of Rehabilitation Measures.
Plasma-Physical D3He Fusion Tandem Reactor Model.
Development of the Low Temperature Technology for Producing Semiconductor Devices on Base of Silicon Carbide
Development and Construction of an Acting Model of Powerful Quasiparallel Pulse X-ray Beam Source for Research, Industrial and Medical Applications.
Development of Construction Concepts for Computerized Control, Monitoring and Diagnostic System for Nuclear Power Plants with Improved Safety.
Use of Coated Particles of High-temperature Reactors in Reactors in Reactor Core of Operated WWER with Purpose of Safety Increase
The Development of Chemical Cycle of Molten Fluoride Salts Reactor Fuel Reprocessing (ATW Concept, Waste Transmutation)
Development of Cathodes Intended for High-Current Electronics on the Base of Intercalated Laminar materials with High Electron Emission
Development of the System for Ex-reactor Heating of Multy-cell Thermoionic Fuel Assemblies and for Obtaining their J-V Characteristics
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.