Gateway for:

Member Countries


#0092Nuclear Rocket System Testing

Testing of feed system for nuclear propulsion technology under consideration for exploration of Mars.

#0352High Temperature Gas Turbine for NPP

Research on High Temperature Component Technologies.

#0425Zirconium Ceramics for Nuclear Reactor

Design of Zircon-based Ceramics for a Nuclear Reactor Core Melt Catcher

#0502Hydraulically Induced Vibrations

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

#0559Lead-Bismuth Target

Pilot Flow Lead-bismuth Target of MW Power for Accelerator-Driven Systems

#0769High-Temperature Recuperator

The Experimental Investigations of a High-temperature High Efficiency Recuperator

#1399Radiation Influence on Ignition of Hydrogen Mixtures

Research of the Impact of Ionising Radiation on Ignition Limits and Burning Rate of Hydrogen-Air and Steam-Hydrogen-Air Gaseous Mixtures

#1486Cascade Subcritical Reactor

Experimental and Theoretical Justification of the Cascade Scheme of the Subcritical Molten-Salt Reactor for Transmutation of Long-Lived RW of the Nuclear Fuel Cycle

#1611Thermohydraulics in Liquid Metal Cooled Reactors

Generalisation of Data on Hydrodynamics and Heat/Mass Transfer Processes in Liquid Metal Cooled Reactors

#1742Sorbents for Radioiodine

Development of Technology for Producing Sorbents Used to Separate Radioiodine from Gas Media

#1828Prompt Neutron Spectra of Minor Actinides

Measurements of the Prompt Neutron Spectra of Minor Actinides. Fast Neutron Induced Fission of 241Am and 243Am, Thermal Neutron Induced Fission of 243Cm

#2936Reactor Core Melting

Modelling of Reactor Core Behaviour under Severe Accident Conditions. Melt Formation, Relocation and Evolution of Molten Pool

#2973Gas Cooled Fast Nuclear Reactor Facility

Development of Conceptual Proposal on Design of Fast Nuclear Gas Cooled Reactor Facility FBGR-1000 with Using of Light Water Reactors and Micro-Coating Fuel Technologies

#3081Mono-block large-sized plates

Development of New Methods of Manufacturing Unique Mono-Block Large-Sized Plates

#3081.2Mono-Block Large-Sized Plates

Development of New Methods of Manufacturing Unique Mono-Block Large-Sized Plates

#3194Fuel Assembly Under Severe Accident Conditions

Fuel Assembly Tests under Severe Accident Conditions

#3213Channel-Type Reactor with Coolant of Supercritical Parameters

Development of the Design Code Package to Analyze Thermohydraulic and Neutronic Characteristics of the Channel-Type Water-Cooled Water-Moderated Reactor with Supercritical Parameters of the Coolant

#3420VVER-1000 Reactor Pressure Vessel

Material Science Work Package for Lifetime Extension of VVER-1000 Reactor Pressure Vessels (RPV) from High Nickel Materials

#3514Removing Corrosion Products from NPP’s Systems

Development of Technology for Separating Corrosion Produced Radionuclides from Water by High-Gradient Magnetic Filtration

#3690Fuel Assemblies under Severe Accident

Study of Fuel Assemblies under Severe Accident Top Quenching Conditions in the PARAMETER-SF Test Series


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