Development of electrokinetic and chemical methods for rehabilitation of soil and ground water contaminated by radionuclides and heavy metals.
Development, Calculation and Experimental Validation of the Lead-Cooled Fast Reactor Concept (including the Comparison of Critical and Subcritical Reactor with External Proton Source)
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.
Strength regulations for ship NPPS and the USA Asme Code (comparative analysis).
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.
The design and construction of a cryostat and vacuum windows for a large liquid Krypton calorimeter for use in high energy physics experiments.
Experimental and calculation investigation to validate the concept of the reactor technology with ultimate neutronics and thermal-hydraulic characteristics.
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.
Development of Safeguarding Devices for Localization of Severe accidents Releases at Nuclear Power Plant.
Functional Training-Simulating Complex of the Research Reactor PIK (FTSC PIK).
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...
Experimental and Theoretical Modeling of a Pure and Safe High Efficiency Laser Driver Fusion Reactor.
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.
The Safety Insurance at Decommissioning of Reactor Installations of Civil and Military Application.
Theoretical and test Analysis of Hydraulically Induced Vibrations in Compact Curling Tube Steam Generators.
Experimental Studies of Reactor Radiation Scattering in the Atmosphere.
The Establishment of Methodology for Determining Residual Resource of NPP Reactors Power Vessels.
Analysis of Accident Evolution and Consequences for the 4th Block Chernobyl Nuclear Power Plant.
Irradiation Growth in Zirconium
The Benchmarks for Mathematical Simulation of Chernobyl-4 Accident
Study of Gas- and Molten-Fluoride Separation and Transmutation for Accelerator Based Plutonium Disposition and Nuclear Waste Treatment
Design and Construction of a Hadron Calorimeter for Use in the H1 Experiment Carried out at the HERA Electron-Proton Collider
Methodical Development for VVER Reactor Pressure Vessel State and Safe Operation Lifetime Evaluation by Fracture Mechanics Criteria
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
The Conception of the Russian Nuclear Powered Submarines Inactivation and Recycling at the State Center of Nuclear Shipbuilding Industry (GRTsAS) Plants
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
Preliminary Project for Exploring Mars
Concept Development of Innovation Technology for Decommissioning of Nuclear Power Plants. Calculation, Experimental, Technical and Economic Studies in Justification of the Concept
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
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
Monograph "Natural Safety Fast Neutron Lead Cooled Reactor for Large Scale Nuclear Power"
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
System Analysis of Uncertainties of Nuclear Safety Characteristics for VVER Reactors with Various Fraction of MOX Fuel in the Core
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
Research and Development of an Optimal Neutron Moderators Configuration for IBR-2M Pulsed Neutron Source
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
Comparative Study of ADS-burners with Fast, Intermediate and Thermal Neutron Spectrum for Radioactive Waste Transmutation
Feasibility Study for the Development and Introduction of Radiation-Safe Technology for Handling Radioactive Graphite of Channel-Type Reactors
Study of Irregular Heterogeneous Effects in an LWR-Type Reactor Core
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.