Database on benchmark calculations of solar and long wave atmospheric radiation transfer parameters for climate studies.
Development of scientific basis and industrial technologies for treating structural materials by ion and plasma beams combination with protective coating.
Development of wide aperture plasma accelerator with a low-flow rate of gas for technical purposes.
#0044Ion beam Recuperator
Ion beam energy recuperator.
Atomic and radiation processes in plasmas, gases and solids
#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.
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.
g-ray Spectroscopy of Tokamak Plasmas.
#0161-2Spectroscopy of Tokomak (C)
g-ray Spectroscopy of Tokamak Plasmas.
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 Reactor Lifetime Precise Calculation Code on Base of Monte-Carlo Method.
Solid State Electrochemical Battery Based on Ionic Conductors of Lanthanum 3-Fluoride Type.
Investigation of the Radiation in Nuclear Fuel Cycle Based on Reprocessed Uranium and Mixed Uranium-Plutonium Fuel.
Development of Technology of Production of Some Temperature and Radiation Resistant sic-based Semiconductor Structures
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...
Research and Development Towards the Technical Design and the Manufacturing of the Inner Track system (ITS) and of the Forward Multiplicity detector (FMD-MCP) for the ALICE Experiment at CERN.
Investigation of Promising Fuel Materials for PWR Having Maneuverable Operating Conditions.
Development of Model of Closed Tritium Loop with Purification Technology, Radiation Resistant Diagnostics and Radiation Shielding, Theoretical and Experimental Simulation of Plasma Effects on Reactor Systems with T-Be Safety Analyses in Support of ITER.
Hybrid Reactor (TEC-NIT) Conceptual Design Development
Investigation of non-thermal Possibilities of Origin of the Superconductivity in High-Energy Pulsed High-gamma-neutron Fluxed.
Design of Zircon-based Ceramics for a Nuclear Reactor Core Melt Catcher
Measurements of Actinide Nuclear Data
Development and Computational-Experimental Validation of the Concept of Self-Quenching Multi-channel Pulse Graphite Reactor (MIGR) for the Studies on Nuclear Reactor Safety.
Development of Methods and Creation of the Equipment Complex for Thermonuclear Plasma Diagnostics at Tokamak by Neutrons and Charged Fusion Products.
Theoretical Fundamentals for Multicomponent Isotope Separation by a Gas Centrifuge.
Analysis of Accident Evolution and Consequences for the 4th Block Chernobyl Nuclear Power Plant.
Radioecological Consequences of Contamination of the Lakes after the Chernobyl Accident and Analysis of Rehabilitation Measures.
Plasma-Physical D3He Fusion Tandem Reactor Model.
Development of Construction Concepts for Computerized Control, Monitoring and Diagnostic System for Nuclear Power Plants with Improved Safety.
The Benchmarks for Mathematical Simulation of Chernobyl-4 Accident
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
Development of Cathodes Intended for High-Current Electronics on the Base of Intercalated Laminar materials with High Electron Emission
Development of the System for Ex-reactor Heating of Multy-cell Thermoionic Fuel Assemblies and for Obtaining their J-V Characteristics
Study of Plasma and Electrophysical Processes in the Pulsed and High Current Discharges for the Development of the Minik Conceptual High Neutron Source Design, Using the Inductive Cascade Storage
Working out of a Method for the Reactor Neutron Spectrum Measurements by Resonance Detectors
Development of Experimental-Numerical Methods and Equipment for Residual Stresses Determination in Welded Pipelines
A Multifactoring Charged Particles Accelerator for Medicine and Industry Applications
Uranium Dioxide Properties/Behavior at High Burnups under Reted and Emergency Conditions Determined through Out-of-Pile Modeling
Development of a Super-Intensive Pulsed Neutron Source for Physics Research RIN-10 on the Basis of the INR RAS Accelerator-Storage System
Nuclear Equation of State with Deconfinement Phase Transition and 3D Relativistic Dissipative Hydrodynamics. Development of the Approach and Confrontation of Results to Experimental Data on Heavy-ion Collisions
Study of the Conditions for the Reactivity Burst Occurrence at the Reflood Phase of a Loss-of-Coolant-Accident in VVER-type Reactors
Development and Studies of Prototypes of Photons Spectrometer Based on Heavy Crystals
Execution of the Complex of Benchmark Experiments for Testing the Nuclear Data of Vanadium - Main Component of Low-Activation Structural Materials for Perspective Nuclear Energetics
Development of High-Effective and Low-Waste Technology of Fission-Fragment 99 Mo Production for Medical Purpose Based on Use of Fluoride Molten Salts
Research of Ways and Development of Magnetoresonance Tomograph with a Pulsed Magnetic Field
The Conception of the Russian Nuclear Powered Submarines Inactivation and Recycling at the State Center of Nuclear Shipbuilding Industry (GRTsAS) Plants
Development, Assembling and Testing of Pilot Plant for Conversion of Uranium Hexe-fluoride Depleted on Isotope U-235 to Uranium Metal and Anhydrous Hydrogen Fluoride
Fuel Elements with Solid Polymer Electrolyte (SPE) Having Efficiency of up to 70%
Development of Principles for Creating and a Process for Manufacturing a High Sensitivity X-ray Apparatus Based on Charge-Coupled Devices
Space Technology for the Centralized Emergency Control. (Monitoring of Nuclear Power Facilities for the Normal Operation and Emergency; Monitoring of the Nuclear Sites' Influence on the Radiation Situation and Other Ecological Factors).
Optimum Strategy for Nuclear Fuel Cycle Development in Russia
Completion of a Closed Tritium Circuit Device, Investigation of Processes, Manufacturing, and Tests of Models of ITER Tritium Loop Components; Experimental Simulation and Theoretical Analysis of Plasma Effects of ITER In-Vessel Structure Components; Radia
Underwater - Underice Systems for Arctic and Far Eastern Offshore Oil and Gas Field Development: Risk Assessment; Study of Methods to Provide Safety
Study of Radiation-Induced Degradation by Swelling of Austenitic Stainless Steel Intravessel Components in Western PWR and Eastern WWER Reactors
Development of GIS-DSS Systems for Research, Education and Training in the Context of the Rehabilitation of Contaminated Territories with Consideration of Radioecological, Ecological, and Socio- Economic Factors. (GIS - Geographical Information system; DS
Validation of Technical Feasibility of Burning Weapon's Grade and Civil PU Via New Generation PWR Fuel Elements Designed in ISTC Project N173-95
Calculations for Validation of Safety and Design of Safety Systems for Helium Modularised Reactor with Gas Turbine ( GT-MHR) and Plutonium as a Fuel
Development of Repetitive Plasma Injectors for a Generator of Superpower Electromagnetic Pulses
Development of Implantation-Plasma Surface Treatment and Creation of the Protecting Coating for the Improvement of High Temperature Oxidation Corrosion Resistance of Gas Turbine Blades and Other Machine Parts Operating Under Sign-Alternating Loading
Atomic Data: Photon Absorption, Electron Scattering, Vacancy Decay
System of Improved Reliability for Detection and Deactivation of Anti-Personal Mines remaining in Place After the End of Military Operations
Development of Efficient Sensor Technology, Prototypes of Gas Sensors and, Based on Them, Improvement of Methods of Explosive and Toxic Gases Monitoring
X-Ray Polarisation Researches of the High Current Z-Pinch Plasma Radiation. Theory and Experiment
Development of Basic Principles of Processing of Plutonium in Fuel PuO2-x -Microspheres with Multi-layer Coating with the Purpose of a Disposition of a Weapons Plutonium with the Substantiation of Their Long-Duration and Safe Storage and/or Burn out in Nu
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
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
Experimental Mock-up of Molten Salt Loop of Accelerator-Based Facility for Transmutation of Radioactive Waste and Conversion of Military Plutonium. Stage 2: Experimental Study of Molten Salt Technology for Safe, Low-Waste and Proliferation Resistant Treat
Feasibility Study of New Low-Waste Technology for the Production of Fission-Fragment Strontium-89 for Medicine
Utilisation of the Energy Released from Processing Municipal Solid Waste for Desalination of Sea Water
Feasibility Study of the Blanket and Fusion Reactor Concept for Transmutation of Minor Actinides and Plutonium
System Analysis of Uncertainties of Nuclear Safety Characteristics for VVER Reactors with Various Fraction of MOX Fuel in the Core
Development of Technology of Sorbtion – Aerosols Fibrous Superfiltres Produce in Electrostatic Poles
The Transport and Technological Plan of the Spent Nuclear Fuel Management in Severodvinsk
New Prospective Materials Based on Wide-Gap Ionic Semiconductor CdF2 for Emitters, Memory Cells, and Holographic Elements
Ozone Pertraction through Non-Porous Polymeric Membranes for Efficient and Energy Saving Treatment of Waste Waters and Disinfection of Drinking Water
An Analysis of Burials of Radioactive Waste in the Territory of the Russian Research Center "Kurchatov Institute" in Moscow and Paths of Supposed Radionuclides Migration in the Environment
Development of Methods, Equipment and Software for Evaluation of Residual Resource of Elements of Nuclear Power Stations and Oil, Gas Pipelines Transport
Study of Opportunities for the Submillimeter Polarizational Spectroscopy in Pulsed Magnetic Fields up to 50 T
Development of a Technology for Large Scale Production of Carbon Nanotubes and Exploration of Use of This Material in Power Engineering
Research and Development of High-Sensitive Semiconductor Gas Sensors and Ionizing-Radiation Detectors for Environment Monitoring
Synchrotron radiation application for oncological diseases risk forecasting
Development of the Basis for Neutron-Physical Calculations of Reactor Value Variances Caused with Uncertainties of Initial Data
Neodymium Isotopes Separation for Searching the Neutrino Mass (2-beta-0-nu-decay of Nd-150)
The Integrated Relational Database of the Nuclear Data Reaction References in the Internet Created on the Base of CINDA, EXFOR Libraries and Other Sources
Developing the Experimental Model of the Device for Nuclear Material Detection by Photoneuton Technology, Optimization of Device Detection Parameters to Meet the Solution of Non-Proliferation Problems
Synthesis of Diamonds from Organic Compounds, Manufacturing of Diamond Compacts and Composites, and the Study of Physical and Chemical Properties of these Materials
Development of Analytic Information System to Carry out Analysis of Health Risk from Technogenic and Natural Sources of Harmful Impact
Evaluation and Integral Validation of Nuclear Data of Tungsten – Candidate Material of Fusion Reactor Diverter
Risk Based Land Management, Rehabilitation and Sustainable Development of Radioactive Contaminated Territories
Hydrogen Trapping and Release at Plasma and Ion Interaction with Solids
Fundamental Studies of Radiation-Induced Processes for Production of Radiation Resistant Structural Materials for Fission and Fusion Reactors and Future Advanced Technologies
Development of Fundamentals and Engineering Solutions of Detection of Explosives (Group of Nitrocyclohydrocarbons) by Micromachined Semiconductor Gas Sensors Using Gas Pre-Concentration System
Development of Analytical Methods of Hydrogen and Helium Embrittlement of Nuclear Reactor Materials and Containers for Storage and Transport of Radioactive Materials
Development and Design of Start Detector for Trigger and Time-of-Flight Systems for the ALICE Experiment at CERN, LHC
Environmentally Friendly Small Capacity Power Plants Based on Fuel Cells for Stationary Application
New Quasicrystal-Based Composite Materials for Industrial Applications
Development of the Models for Nuclear Fuel Behavior During Active Phase of Chernobyl Accident
Pinch-Effect in Laser Produced Plasma
Development of Concept and Methodology for Assessing Risk of Nuclear Weapon Proliferation through Civilian Nuclear Power Systems
Development of Physical Bases of New Technologies of Nitrogen and Carbon Isotopes Production by Nonequilibrium Reactions Proceeding in a Post-Discharge Zone
Liquid Metal Coolant for High-Temperature Fast Reactors
Experimental and Theoretical Verification of a Precision Method for Electronic Controlling the RedOx-Potential of Molten Salts for Reactors, Transmutation of Long-Lived RW, and Non-Aqueous Reprocessing SNF
Theoretical Substantiation of Vacancy Doping Oxide Fuel for its Deep Burn Up into PWR
Development of Conceptual Proposal on Design of Fast Nuclear Gas Cooled Reactor Facility FBGR-1000 with Using of Light Water Reactors and Micro-Coating Fuel Technologies
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)
Theoretical and Conceptual Substantiation of Deep-Burnable Glass Micro-Fuel for Fast Reactors
Ecological Safety by Dismantling Nuclear Powered Submarines (Damaged Included) in Primorsky Krai
Measurement and Evaluation of Cross Section for Minor Actinides in Low Energy Region
The Development of Composition and Technology of Amendment Production for Rehabilitation of Soils Contaminated by Radionuclides and Assessment of Their Application Efficiency
Research into the Mechanisms of Structural-functional Stability of Human Tissues Exposed to Heavy Metals
Experimental Determination of the Yields of Molecular Products in Water Irradiated by Accelerated Protons in the Test Bench "PROTOKA" at Supercritical Pressure and Temperatures 280-500 °C
Radiation Investigation of Nuclear Dangerous and Radiation Dangerous Objects of the Russian Research Center «Kurchatov Institute» for Scheduling of Works on Their Decommissioning
Development of Calculation Methodology Used in Computing Nuclear-Physics Characteristics of Nuclear Reactor Cells and Assemblies Containing MOX Fuel, and in Unstructured Grids for Nuclear Safety of Reactor Facilities
Material Science Work Package for Lifetime Extension of VVER-1000 Reactor Pressure Vessels (RPV) from High Nickel Materials
Development of Novel Technology for Instrumental Control of the Forest Ecosystems Сarbon Balance in Remote Areas
Comparative Study of ADS-burners with Fast, Intermediate and Thermal Neutron Spectrum for Radioactive Waste Transmutation
Analysis of the Methodical Part of Uncertainty of Neutron-Physics Calculation of Transient Processes for Next Generation Reactors and Fuel Cycles
Technical and Economic Feasibility of Alternatives for the Packaging, Interim Storage & Transportation of Fresh and Spent MOX Nuclear Fuel
Development of Experimental Model of Portable Device for Identification of Explosives Hidden in Soil and Buildings by Tagged Neutron Technology
Quantum Information Processing Devices on the Base of Optical Transients and Collective Phenomena for Optical Communication: Research and Development
Long-term Behavior of Corium after Accident (Using the Data of the Chernobyl NPP Accident)
Development of Information, Legal and Regulatory Basis for a System of the Institutional Control and Stewardship Of Radioactively Contaminated Areas and Radionuclide Ionizing Radiation Sources in the Russian Federation
Experimental Study on Critical Issues of Nuclear Energy Systems Employing Liquid Salt Fluorides
Development of the Fusion Core Plasma Electric Potential Diagnostics
New Materials and Heterostructures for Conductometric Sensors of Fluorine and Hydrogen Fluoride
Investigation of Helium and Hydrogen Embrittlement and Early Diagnostic Methods Development for Reactor Materials Embrittlement
Intrinsic Room Temperature Ferromagnetism, Magnetic Moments and Magneto-Optical Effects in Elemental and Oxide Semiconductors
Dust Technologies for Thermonuclear Fusion
Development of Physical Principles and Creation of Active Elements of Semiconducting Spintronics Based on Magnetic Nanostructures
Examination of the ETDR Engineering Decisions, Development of Proposals for their Improvement, Analytical and Experimental Studies of Properties of Advanced Fuel and Materials of GCFR Fuel Assembly in the BOR-60
Cross-Verification and Analysis of Accuracy of Neutron-Physical Codes for Nuclear Reactors RBMK and CANDU
Meeting Energy Needs in Selected European Countries Faced with a Shortage of Raw Material Resources
Assessment of Radiation Impacts of the Radioactive Waste Storage Sites of Specialized Enterprises "Radon" within 50 km Monitoring Zones
Investigation of Onion-Like Carbon Nanoparticles Produced from Nanodiamonds of Detonation Synthesis and Development of Composites with their Application
Development of Plants for the Production of Highly Concentrated Boron Isotopes and Synthesis of Boric Acid Labeled with Boron-10 and Boron-11 Isotopes; Development of the Process for the Production of Highly Pure Elementary Boron.
Comprehensive analysis of the spin transport in discrete alloys „semiconductor – ferromagnet“ with controlled disorder
Synthesis and Comprehensive Analysis of Novel Polymer Nanocomposites for Microsensors
Development of Personnel Gamma-Neutron Emergency EPR Dosimeter with Separation of Various Radiation Components Portion and Methods of Local Dosimetry at Neutron-Capture Therapy
Development and Tests of a Personal Tissue-Equivalent Emergency Dosimeter for the Staff of Nuclear and Radiation Hazardous Development and Tests Establishments
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.