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#0101-2Ocean Nuclear Data Base (C)

Development of scientific and methodological basis for diagnostics and forecast of the state of Nuclear Waste at the bottom of the Barents and Kara Seas and the Sea of Japan. Identification of Ways to Prevent Dangerous Ecological Aftereffects.

#0220Fast Sodium Reactors

Studies of Physics and Engineering Problems for Safety Increase and Burning of Actinides Efficiency for Advanced Fast Reactors.

#0269Modular Helium Reactor

Development of Conceptual Design of Modular Helium Reactor with Gas Turbine (GT-MHR).

#0352High Temperature Gas Turbine for NPP

Research on High Temperature Component Technologies.

#0369Economics of Plutonium Burn

Study on the Feasibility and Economics of the Use of Ex-Weapons Plutonium and Civil Plutonium as Fuel for both Fast and Thermal Reactors.

#0435Pumps for Oil Extraction

Development of Enhanced Reliability Well Pumps for Oil Production.

#0502Hydraulically Induced Vibrations

Theoretical and test Analysis of Hydraulically Induced Vibrations in Compact Curling Tube Steam Generators.

#0650Safety of Advanced Fast Reactors

Study on the Physical and Engineering Problems Concerning the Increase in Safety and Actinides Burning Efficiency of Advanced Fast Reactor

#0685.2Self-protection of Reactors

Nuclear Safety and Inherent Self-Protection Investigations for Modular High Temperature Gas-Cooled Reactors (HTGR-M)/Experimental Demonstration in the ASTRA Facility of the Inherent Safety Characteristics of HTR's

#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

#0769High-Temperature Recuperator

The Experimental Investigations of a High-temperature High Efficiency Recuperator

#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

#1261Turbogenerator for Helium Cooled Reactor

Calculation - Structural Investigation for Validation of GT-MHR Reactor Plant Turbogenerator Serviceability

#1313Materials for High Temperature Turbocompressor Components

Testing and Investigations of Materials for GT-MHR Turbocompressor High-Temperature Components

#1431Intensive Neutrino Source

Calibration and Testing of the Technology for the Preparation of an Intense Neutrino Source Based on AR-37 Isotope as well as for the Calibration of an Iodine Detector of Solar Neutrinos

#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

#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

#2111The Environmental Assessment of "Nerpa" Ship Repair Yard

The Environmental Assessment of “Nerpa” Ship Repair Complex (Including Facilities for Spent Nuclear Fuel and Radioactive Waste Handling) and Development of the Proposals for Improving the Spent Nuclear Fuel and Radioactive Waste Management and the Ecologi

#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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