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#0064Concrete Protection of Reactors

Design of a nuclear reactor core melt catcher on the basis of zirconia concrete.

#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.

#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.

#0425Zirconium Ceramics for Nuclear Reactor

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

#0559Lead-Bismuth Target

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

#0564Temperature of Water-cooled Reactor

Methodological Security of Temperature Measurement and Diagnostics within Power Water-moderated Water-cooled Reactor (PWR) Type on Base of Analysis of Influence Functions for Measuring Means.

#0797.2Safe Operation of VVER Reactor

Methodical Development for WWER-1000 Reactor Pressure Vessel Safe Operation Lifetime Evaluation Allowing for Anticorrosive Cladding

#0939Catcher for the Molten Core

Design of a Catcher for the Molten Reactor Core at an NPP on the Basis of Zirconia Concrete

#0941Database on Fission Products Release

Creation of a Database for Computational Codes, Realizing Detailed Mathematical Modeling of a Radioactive Fission Products Realize from Fuel Rods VVER 440, VVER 1000

#1679Radiation Safety Thermal-Hydraulic Codes

Verification of Thermal and Hydraulic Codes, Used for Safety Justification of Russian VVER NPPs

#2105Boron Dilution in WWER Reactors

Study of Emergency Situations Related to Boron Dilution in WWER Reactors

#3194Fuel Assembly Under Severe Accident Conditions

Fuel Assembly Tests under Severe Accident Conditions

#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

#3780Reactor Temperature Control

Modernization of Metrological Security of Reactor Thermometry Taking into Account Quality of Thermal Contact Between Thermocouple and Object and Degradation of its Characteristics at Irradiation

#3936Fuel Assemblies under Severe Accident Conditions

Study of Fuel Assemblies with Boron Carbide Absorber Rods under Severe Accident Conditions in the PARAMETER-SF Tests 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.

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