Gateway for:

Member Countries


#0071Validation of Lead-Cooled Reactors

Development, Calculation and Experimental Validation of the Lead-Cooled Fast Reactor Concept (including the Comparison of Critical and Subcritical Reactor with External Proton Source)

#0365Laser Driver Fusion Reactor

Experimental and Theoretical Modeling of a Pure and Safe High Efficiency Laser Driver Fusion Reactor.

#0566Residual of NPP-Reactors

The Establishment of Methodology for Determining Residual Resource of NPP Reactors Power Vessels.

#0569Chernobyl Accident Analysis

Analysis of Accident Evolution and Consequences for the 4th Block Chernobyl Nuclear Power Plant.

#0681Irradiation Growth in Zr

Irradiation Growth in Zirconium

#0747Fluoride Technology for Transmutation

Study of Gas- and Molten-Fluoride Separation and Transmutation for Accelerator Based Plutonium Disposition and Nuclear Waste Treatment

#0788Hadron Calorimeter for HERA-H1

Design and Construction of a Hadron Calorimeter for Use in the H1 Experiment Carried out at the HERA Electron-Proton Collider

#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

#0970Conditions of Ignition and Combustion of Graphite in NPP-Reactor

Theoretical and Experimental Investigation of Ignition and Combustion of Reactor Graphite under Conditions of Accident at the Fourth Reactor of the Chernobyl Nuclear Power Plant

#1294Laser Technology for Remote Treatment of Atomic Equipment

Investigation of Interaction of Laser Radiation with Radioactive Deposits on the metal Surface and Creation of Experimental Stand for Development of Laser Technology for Remote Treatment of Materials Contaminated with Radioactive Substances at the Atomic

#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

#2787Moderators for Pulsed Neutron Source

Research and Development of an Optimal Neutron Moderators Configuration for IBR-2M Pulsed Neutron Source

#3574Accelerator-Driven Systems for Transmutation

Comparative Study of ADS-burners with Fast, Intermediate and Thermal Neutron Spectrum for Radioactive Waste Transmutation

#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.

Promotional Material

Значимы проект

See ISTC's new Promotional video view