#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.
#0220Fast Sodium Reactors
Studies of Physics and Engineering Problems for Safety Increase and Burning of Actinides Efficiency for Advanced Fast Reactors.
Development of Conceptual Design of Modular Helium Reactor with Gas Turbine (GT-MHR).
Research on High Temperature Component Technologies.
Study on the Feasibility and Economics of the Use of Ex-Weapons Plutonium and Civil Plutonium as Fuel for both Fast and Thermal Reactors.
Development of Enhanced Reliability Well Pumps for Oil Production.
Theoretical and test Analysis of Hydraulically Induced Vibrations in Compact Curling Tube Steam Generators.
Study on the Physical and Engineering Problems Concerning the Increase in Safety and Actinides Burning Efficiency of Advanced Fast Reactor
#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
Conceptual Studies for Use of High-Enriched (Weapon-Grade) Uranium and Plutonium and Power Plutonium under Conversion of Thermal Reactors to the Closed Thorium-Uranium Cycle
The Experimental Investigations of a High-temperature High Efficiency Recuperator
Development of a Super-Intensive Pulsed Neutron Source for Physics Research RIN-10 on the Basis of the INR RAS Accelerator-Storage System
Development of Effective Plasma Radiators of Low-Frequency Electromagnetic Waves for the Satellite-Based Geological Prospecting
Methods and Facilities for Subsurface Microwave Radiothermometry: Diagnostics, Monitoring and Environmental Applications
Testing and Research of 10X9MFB Steel and Its Welded Joints for Application in Reactor Plants with an HTGR and Gas Turbine
Calculations for Validation of Safety and Design of Safety Systems for Helium Modularised Reactor with Gas Turbine ( GT-MHR) and Plutonium as a Fuel
Calculation - Structural Investigation for Validation of GT-MHR Reactor Plant Turbogenerator Serviceability
Testing and Investigations of Materials for GT-MHR Turbocompressor High-Temperature Components
Calibration and Testing of the Technology for the Preparation of an Intense Neutrino Source Based on AR-37 Isotope as well as for the Calibration of an Iodine Detector of Solar Neutrinos
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
Development of Technology for Creation of Neutrino Source on the Basis of 51Cr Isotope with Activity not less than 8 MCi, Using an L2 Heavy Water Reactor for Calibration of Solar Neutrino Detectors
Low Enrichment Uranium Core for Floating Nuclear Power Plant Reactor (FNPP) as a way of Resolving Weapon’s Nuclear Material Nonproliferation Problem
Conduction of Experimental Studies of Heat Exchange Element of Plate-Type Heat Exchanger Aiming at Enhancement of its Effectiveness Owing to Design Improvement and Optimization of Used Heat Exchange Intensifiers
The Environmental Assessment of “Nerpa” Ship Repair Complex (Including Facilities for Spent Nuclear Fuel and Radioactive Waste Handling) and Development of the Proposals for Improving the Spent Nuclear Fuel and Radioactive Waste Management and the Ecologi
The Transport and Technological Plan of the Spent Nuclear Fuel Management in Severodvinsk
Experimental Studies of "Gas-Water" Heat Exchangers with Heat Exchange Surface of Steeply Curved Self-Spacer Coils
Calculational-Theoretical and Design Studies, Preparation of Experimental Works on the Substantiation of the Conceptual Design of Small Power Installation MARS (Autonomous Molten-Salt Reactor with Micro-Particle Fuel)
Creation of Gas Seal for Shaft
Experimental Investigation of Models of Enhanced Compact Heat Exchangers for High Temperature Facility Recuperator Application
Feasibility Study for the Development and Introduction of Radiation-Safe Technology for Handling Radioactive Graphite of Channel-Type Reactors
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