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#0016Soil Decontamination

Development of electrokinetic and chemical methods for rehabilitation of soil and ground water contaminated by radionuclides and heavy metals.

#0071Validation of Lead-Cooled Reactors

Development, Calculation and Experimental Validation of the Lead-Cooled Fast Reactor Concept (including the Comparison of Critical and Subcritical Reactor with External Proton Source)

#0075Acoustic Devices for Reactor Control

Development of acoustic sensor equipment for tightness checks at NPP.

#0101-2Ocean Nuclear Data Base (C)

Development of scientific and methodological basis for diagnostics and forecast of the state of Nuclear Waste at the bottom of the Barents and Kara Seas and the Sea of Japan. Identification of Ways to Prevent Dangerous Ecological Aftereffects.

#0109Strength Regulations for Ship Reactors

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

#0116Verification of Reactor Data Bases (R)

Development of methodical and calculation technology verification of nuclear data bases used in the calculation of neutron-physical characteristics and in analysis of nuclear safety of reactor facilities and nuclear conversion technological processes.

#0121Krypton Calorimeter

The design and construction of a cryostat and vacuum windows for a large liquid Krypton calorimeter for use in high energy physics experiments.

#0134Transmutation in Fast Reactors

Experimental and calculation investigation to validate the concept of the reactor technology with ultimate neutronics and thermal-hydraulic characteristics.

#0180Non-Uniform Shielding of Fusion Reactors

Experimental and Calculational Studies of Nonuniform Shieldings of Fusion Reactors and Development on this Basis of a Set of Benchmark Type Experiments for Codes Verification.

#0282Safeguarding Devices for NPP

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

#0321Research and Training Reactor PIK

Functional Training-Simulating Complex of the Research Reactor PIK (FTSC PIK).

#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...

#0365Laser Driver Fusion Reactor

Experimental and Theoretical Modeling of a Pure and Safe High Efficiency Laser Driver Fusion Reactor.

#0455Hadron Calorimeter Endcap

Development of the Technology and Control of Electron-Beam Welding Procedure and Production of Full Scale Sector of Endcap CMS Hadron Calorimeter. Preparation for Mass Production.

#0465Radioactive Safety under Reactors Decommissioning

The Safety Insurance at Decommissioning of Reactor Installations of Civil and Military Application.

#0502Hydraulically Induced Vibrations

Theoretical and test Analysis of Hydraulically Induced Vibrations in Compact Curling Tube Steam Generators.

#0517Skyshine Shielding Experiments

Experimental Studies of Reactor Radiation Scattering in the Atmosphere.

#0566Residual of NPP-Reactors

The Establishment of Methodology for Determining Residual Resource of NPP Reactors Power Vessels.

#0569Chernobyl Accident Analysis

Analysis of Accident Evolution and Consequences for the 4th Block Chernobyl Nuclear Power Plant.

#0681Irradiation Growth in Zr

Irradiation Growth in Zirconium

#0683Benchmarks for Chernobyl Simulation

The Benchmarks for Mathematical Simulation of Chernobyl-4 Accident

#0747Fluoride Technology for Transmutation

Study of Gas- and Molten-Fluoride Separation and Transmutation for Accelerator Based Plutonium Disposition and Nuclear Waste Treatment

#0788Hadron Calorimeter for HERA-H1

Design and Construction of a Hadron Calorimeter for Use in the H1 Experiment Carried out at the HERA Electron-Proton Collider

#0797Safe Operation of VVER Reactor

Methodical Development for VVER Reactor Pressure Vessel State and Safe Operation Lifetime Evaluation by Fracture Mechanics Criteria

#0816Super-Intensive Neutron Source

Development of a Super-Intensive Pulsed Neutron Source for Physics Research RIN-10 on the Basis of the INR RAS Accelerator-Storage System

#0897Remediation of Soils

Complexant Enhanced Electrokinetic Remediation of Soils Contaminated with Organics

#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

#0970Conditions of Ignition and Combustion of Graphite in NPP-Reactor

Theoretical and Experimental Investigation of Ignition and Combustion of Reactor Graphite under Conditions of Accident at the Fourth Reactor of the Chernobyl Nuclear Power Plant

#1172Mars Expedition

Preliminary Project for Exploring Mars

#1192New Concept of Reactor Decommissioning

Concept Development of Innovation Technology for Decommissioning of Nuclear Power Plants. Calculation, Experimental, Technical and Economic Studies in Justification of the Concept

#1243Radioactive Graphite Handling

Technical and Economic Grounds for the Development and Introduction of Radiation Safe Technology for Handling and Treatment of Spent Radioactive Graphite from RBMK-Type Reactors

#1294Laser Technology for Remote Treatment of Atomic Equipment

Investigation of Interaction of Laser Radiation with Radioactive Deposits on the metal Surface and Creation of Experimental Stand for Development of Laser Technology for Remote Treatment of Materials Contaminated with Radioactive Substances at the Atomic

#1418Lead Cooled Reactor with Inherent Safety

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

#1446Radiowaste Disposal in the Permafrost

Development and Substation of Main Technical Solution for Underground Isolation of Permafrost of Radioactive Wastes Including Reactor Sections of Decommissioned Nuclear Submarines and Ice-Breakers and Spent Nuclear Fuel, Not Intended for Reprocessing, For

#1836Nuclear Safety of MOX Fueled VVER

System Analysis of Uncertainties of Nuclear Safety Characteristics for VVER Reactors with Various Fraction of MOX Fuel in the Core

#2267Creation of Subcritical Assembly Driven by Proton Accelerator (SAD)

Construction of the Subcritical Assembly with Combined Neutron Spectra Driven by Proton Accelerator at Proton’s Energy 660 MeV for Experiments on Long Lived Fission Products and Minor Actinides transmutation (Phase I: Design, Design Documentation and Safe

#2787Moderators for Pulsed Neutron Source

Research and Development of an Optimal Neutron Moderators Configuration for IBR-2M Pulsed Neutron Source

#3213Channel-Type Reactor with Coolant of Supercritical Parameters

Development of the Design Code Package to Analyze Thermohydraulic and Neutronic Characteristics of the Channel-Type Water-Cooled Water-Moderated Reactor with Supercritical Parameters of the Coolant

#3574Accelerator-Driven Systems for Transmutation

Comparative Study of ADS-burners with Fast, Intermediate and Thermal Neutron Spectrum for Radioactive Waste Transmutation

#3607Radioactive Graphite Handling

Feasibility Study for the Development and Introduction of Radiation-Safe Technology for Handling Radioactive Graphite of Channel-Type Reactors

#3814Irregular Heterogeneous Effects in a LWR Reactor

Study of Irregular Heterogeneous Effects in an LWR-Type Reactor Core

#3896Thermohydraulics in a Bundle of Rods at Supercritical Parameters of Water

Experimental Studies of Thermohydraulic Processes in a Bundle of Rods as Applied to Channel-Type Reactor Conditions at Supercritical Parameters of Water

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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