Theoretical and numerical models of severe nuclear reactor accidents due to inadvertent reactivity insertion and calculation of the radioactive pollution source parameters.
System design for safeguarding nuclear materials utilized at complex nuclear facilities.
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.
Strength regulations for ship NPPS and the USA Asme Code (comparative analysis).
Initiation and development of chemical (chain and thermal) explosions in reactors and energy-producing apparatus.
Development of Safeguarding Devices for Localization of Severe accidents Releases at Nuclear Power Plant.
Investigation of Explosive Melt-Water Interaction (Steam Explosion) under Severe Accidents at NPPs with Light Water Reactors.
Development of a Computerized Nuclear Control and Accounting for Implementation in Russian Facilities.
Study on the Physical and Engineering Problems Concerning the Increase in Safety and Actinides Burning Efficiency of Advanced Fast Reactor
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
Development of Methods for Creation and Registration of Unique Recognizable Optical Images for Nuclear Material Control
Investigation of Corium Melt Interaction with NPP Reactor Vessel Steel (Metcor)
Investigation of Corium Melt Interaction with NPP Reactor Vessel Steel (METCOR)
Development of a Technical Design for DU-shielded Transport Cask with Increased Spent Nuclear Fuel Specific Loading
The Conception of the Russian Nuclear Powered Submarines Inactivation and Recycling at the State Center of Nuclear Shipbuilding Industry (GRTsAS) Plants
Dose, Temperature and Reliability Monitoring on Electrical Equipment for Nuclear Power Plants and Space Communication Systems
Development of Technology for Metal Surface Decontamination in Aqueous Solutions
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.