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#0003Modeling Nuclear Accidents

Theoretical and numerical models of severe nuclear reactor accidents due to inadvertent reactivity insertion and calculation of the radioactive pollution source parameters.

#0040Nuclear Materials Accounting

System design for safeguarding nuclear materials utilized at complex nuclear facilities.

#0065Reactor Accident Loading

Technique of forecasting loads on nuclear reactor containment during severe accident conditions.

#0066Reactor Wall Loading

Accelerated flame propagation and deflagration-detonation transition in large volumes of hydrogen-steam-air mixtures with aim to determine and reduce loads on nuclear reactor containment under severe accident conditions.

#0109Strength Regulations for Ship Reactors

Strength regulations for ship NPPS and the USA Asme Code (comparative analysis).

#0124Chemical Explosions

Initiation and development of chemical (chain and thermal) explosions in reactors and energy-producing apparatus.

#0282Safeguarding Devices for NPP

Development of Safeguarding Devices for Localization of Severe accidents Releases at Nuclear Power Plant.

#0408Explosive Melt-Water Interaction

Investigation of Explosive Melt-Water Interaction (Steam Explosion) under Severe Accidents at NPPs with Light Water Reactors.

#0560Software for Nuclear Control

Development of a Computerized Nuclear Control and Accounting for Implementation in Russian Facilities.

#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

#0685Self-protection of Reactors

Research of Nuclear Safety and Inherent Safety of High-temperature Gas-cooled Modular Type Reactors (HTGR-M).

#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

#0772Optical Control of Nuclear Materials

Development of Methods for Creation and Registration of Unique Recognizable Optical Images for Nuclear Material Control

#0833Corium Interaction with Reactor Vessel

Investigation of Corium Melt Interaction with NPP Reactor Vessel Steel (Metcor)

#0833.2Corium Interaction with Reactor Vessel

Investigation of Corium Melt Interaction with NPP Reactor Vessel Steel (METCOR)

#0963Uranium Container for Fuel Transportation

Development of a Technical Design for DU-shielded Transport Cask with Increased Spent Nuclear Fuel Specific Loading

#0968Concept of Nuclear Submarines Utilization

The Conception of the Russian Nuclear Powered Submarines Inactivation and Recycling at the State Center of Nuclear Shipbuilding Industry (GRTsAS) Plants

#1003Monitoring of Electrical Equipment of NPPs

Dose, Temperature and Reliability Monitoring on Electrical Equipment for Nuclear Power Plants and Space Communication Systems

#1222Surface Decontamination by Solution

Development of Technology for Metal Surface Decontamination in Aqueous Solutions

#1246Nondestructive Burnup Measurements

Nondestructive Control of a Burnup Depth of Spent Fuel for RBMK-1000 Reactors in Storage Pond of Nuclear Power Plants


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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