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#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.

#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

#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

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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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