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#0435Pumps for Oil Extraction

Development of Enhanced Reliability Well Pumps for Oil Production.

#0816Super-Intensive Neutron Source

Development of a Super-Intensive Pulsed Neutron Source for Physics Research RIN-10 on the Basis of the INR RAS Accelerator-Storage System

#0862Space Based Plasma Radiators

Development of Effective Plasma Radiators of Low-Frequency Electromagnetic Waves for the Satellite-Based Geological Prospecting

#1098Subsurface Microwave Radio Thermometry

Methods and Facilities for Subsurface Microwave Radiothermometry: Diagnostics, Monitoring and Environmental Applications

#1194Special Steel and Welded Joints for Reactors

Testing and Research of 10X9MFB Steel and Its Welded Joints for Application in Reactor Plants with an HTGR and Gas Turbine

#1257Safety of Helium Cooled Reactor

Calculations for Validation of Safety and Design of Safety Systems for Helium Modularised Reactor with Gas Turbine ( GT-MHR) and Plutonium as a Fuel

#1446Radiowaste Disposal in the Permafrost

Development and Substation of Main Technical Solution for Underground Isolation of Permafrost of Radioactive Wastes Including Reactor Sections of Decommissioned Nuclear Submarines and Ice-Breakers and Spent Nuclear Fuel, Not Intended for Reprocessing, For

#1586Heavy Water Reactor Neutrino Source

Development of Technology for Creation of Neutrino Source on the Basis of 51Cr Isotope with Activity not less than 8 MCi, Using an L2 Heavy Water Reactor for Calibration of Solar Neutrino Detectors

#0723-2Recycling Weapon-grade U and Pu in U-Th Closed-cycle Reactors

Conceptual Studies for Use of High-Enriched (Weapon-Grade) Uranium and Plutonium and Power Plutonium under Conversion of Thermal Reactors to the Closed Thorium-Uranium Cycle

#2016Floating NPP with Low Enrichment Fuel

Low Enrichment Uranium Core for Floating Nuclear Power Plant Reactor (FNPP) as a way of Resolving Weapon’s Nuclear Material Nonproliferation Problem

#2054Plate-Type Heat Exchanger

Conduction of Experimental Studies of Heat Exchange Element of Plate-Type Heat Exchanger Aiming at Enhancement of its Effectiveness Owing to Design Improvement and Optimization of Used Heat Exchange Intensifiers

#2112Spent Fuel Handling in Severodvinsk

The Transport and Technological Plan of the Spent Nuclear Fuel Management in Severodvinsk

#2989Heat Exchanger with Steeply Curved Coils

Experimental Studies of "Gas-Water" Heat Exchangers with Heat Exchange Surface of Steeply Curved Self-Spacer Coils

#3012Molten-Salt Reactor with Micro-Particle Fuel

Calculational-Theoretical and Design Studies, Preparation of Experimental Works on the Substantiation of the Conceptual Design of Small Power Installation MARS (Autonomous Molten-Salt Reactor with Micro-Particle Fuel)

#3338Turbomachine Shaft Gas Seal

Creation of Gas Seal for Shaft

#3388Compact Heat Exchangers

Experimental Investigation of Models of Enhanced Compact Heat Exchangers for High Temperature Facility Recuperator Application

#3607Radioactive Graphite Handling

Feasibility Study for the Development and Introduction of Radiation-Safe Technology for Handling Radioactive Graphite of Channel-Type Reactors


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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