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#0517Skyshine Shielding Experiments

Experimental Studies of Reactor Radiation Scattering in the Atmosphere.

#1372Transmutation Effectiveness of Nuclear Waste

Complex Radiochemical and Activation Analysis of Long-life Nuclear Waste Transmutation in Fast Reactors and in the Beams of High Energy Accelerators

#1602Publication of Monography on Pulse Reactors

Issue of the Monography "Pulsed Reactors in the RFNC-ITP" (final stage of ISTC project 276-96)

#1836Nuclear Safety of MOX Fueled VVER

System Analysis of Uncertainties of Nuclear Safety Characteristics for VVER Reactors with Various Fraction of MOX Fuel in the Core

#1932Nuclear Safety for Advanced Neutron Sources

Theoretical and Experimental Substantiation of Nuclear Safety for Advanced Pulsed Neutron Sources

#1951Preclinical NCT Studies

Preclinical Neutron Capture Therapy Studies at the MEPhI IRT Nuclear Reactor

#2267Creation of Subcritical Assembly Driven by Proton Accelerator (SAD)

Construction of the Subcritical Assembly with Combined Neutron Spectra Driven by Proton Accelerator at Proton’s Energy 660 MeV for Experiments on Long Lived Fission Products and Minor Actinides transmutation (Phase I: Design, Design Documentation and Safe

#2405Experimental Nuclear-Physics Data for Transmutation

Experimental Researches of Nuclear-Physics Characteristics of Materials Essential for the Processes of Weapon Plutonium Utilization and Radioactive Wastes Transmutation

#2582Actinides Transmutation Study at Critical Assembly

Experimental Study of Minor Actinides Transmutation Problem at BFS-73-1 Fast Critical Assembly

#3094Control of subcriticality of neutron multiplying systems

Development of experimental Prototype of Equipment and Measuring Technique for Control of Subcriticality of Neutron Multiplying Systems

#3194Fuel Assembly Under Severe Accident Conditions

Fuel Assembly Tests under Severe Accident Conditions

#3341Neutron Capture Therapy at the MEPhI

Implementation of an Irradiation Base for Clinical Studies on Neutron Capture Therapy at the IRT MEPhI Nuclear Reactor with use of an Epithermal and Thermal Neutron Beam

#3345Ex-Vessel Source Term ANalysis (EVAN)

Source Term Assessment at Ex-vessel Stage of Severe Accident

#3420VVER-1000 Reactor Pressure Vessel

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

#3592Corium Melt Interaction with Reactor Vessel Steel

Investigation of Corium Melt Interaction with NPP Reactor Vessel Steel

#3635VVER Vessel in Severe Accident

Scale Experimental Investigation of the Thermal and Structural Integrity of the VVER Pressure Vessel Lower Head in Severe Accident

#3690Fuel Assemblies under Severe Accident

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

#3813Phase Relations in Corium Systems

Phase Relations in Corium Systems

#K-1265IN-VEssel COrium Retention (INVECOR) in accident of water reactor

Experimental Study of the Processes at the Corium Melt Retention in the Reactor Pressure Vessel


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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