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.
Design of a Catcher for the Molten Reactor Core at an NPP on the Basis of Zirconia Concrete
Creation of a Database for Computational Codes, Realizing Detailed Mathematical Modeling of a Radioactive Fission Products Realize from Fuel Rods VVER 440, VVER 1000
Verification of Thermal and Hydraulic Codes, Used for Safety Justification of Russian VVER NPPs
Study of Emergency Situations Related to Boron Dilution in WWER Reactors
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
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.