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#0073Self Quenching Pulse Reactors

Monograph on self-quenching pulsed reactors.

#0220Fast Sodium Reactors

Studies of Physics and Engineering Problems for Safety Increase and Burning of Actinides Efficiency for Advanced Fast Reactors.

#0269Modular Helium Reactor

Development of Conceptual Design of Modular Helium Reactor with Gas Turbine (GT-MHR).

#0276Monograph on Pulse Reactors

Preparation of Handwriting of Book "Pulsed Reactors in RFNC-ITP. History, Working, Exploration, Investigation".

#0335Nuclear Propulsion System for Mars Mission

Development of the Conceptual Project of Nuclear Thermal Power Propulsion System (NTPP) for Space Exploration. Conducting of Fuel Testing in the IVV-2 Reactor. Development of Principles to Ensure Nuclear and Radiation Safety of NTPP...

#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

#0909Two-Cascade Power Blanket

Investigation of Neutron Multiplication in Media for Development of a Double-Cascade Frequency Power Blanket

#0909-2Two-Cascade Power Blanket

Study of Neutron Multiplication in Media for Creating a Frequency Two-Cascade Energy Blanket

#1140Publishing of Monograph on Pulse Reactors

Publication of Monograph "Aperiodic Pulse Reactors"

#1261Turbogenerator for Helium Cooled Reactor

Calculation - Structural Investigation for Validation of GT-MHR Reactor Plant Turbogenerator Serviceability

#1418Lead Cooled Reactor with Inherent Safety

Monograph "Natural Safety Fast Neutron Lead Cooled Reactor for Large Scale Nuclear Power"

#1486Cascade Subcritical Reactor

Experimental and Theoretical Justification of the Cascade Scheme of the Subcritical Molten-Salt Reactor for Transmutation of Long-Lived RW of the Nuclear Fuel Cycle

#1821Monograph on Coupled Pulsed Reactor Systems

Preparation of the Scientific Monograph "Coupled Pulsed Reactor Systems"

#1828Prompt Neutron Spectra of Minor Actinides

Measurements of the Prompt Neutron Spectra of Minor Actinides. Fast Neutron Induced Fission of 241Am and 243Am, Thermal Neutron Induced Fission of 243Cm

#2213Fission Cross Sections of Tungsten Isotopes

Measurements of Proton- and Neutron-Induced Fission Cross Sections of Separated Tungsten Isotopes and Natural Tungsten in 50-200 MeV Energy Region

#2410Monograph "Aperiodic Pulse Reactors" (English)

Preparation of the Monograph "Aperiodic Pulse Reactors" for Publication in English

#3192Fission Fragments of Th-232 and U-238

Measurements of Mass, Energy and Angular Distributions of Fragments from Neutron-Induced Fission of Th-232 and U-238 and Creation of Intermediate Energy Nuclear Data Files for ADS Research

#3363Fragments of Fission by Intermediate Energy Neutrons

Developing the Experimental Database on Fragment Yield in Fission of the Main Nuclear Fuel Isotopes and other Minor Actinides Induced by Intermediate Energy Neutrons

#3635VVER Vessel in Severe Accident

Scale Experimental Investigation of the Thermal and Structural Integrity of the VVER Pressure Vessel Lower Head in Severe Accident


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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