Feasibility study of technologies for accelerator based conversion of military plutonium and long-lived radioactive waste.
Study of the Interaction Between Tritium and Candidate Materials for Use in Fusion Reactors
System design for safeguarding nuclear materials utilized at complex nuclear facilities.
Development, Calculation and Experimental Validation of the Lead-Cooled Fast Reactor Concept (including the Comparison of Critical and Subcritical Reactor with External Proton Source)
Experimental and calculation investigation to validate the concept of the reactor technology with ultimate neutronics and thermal-hydraulic characteristics.
Development of process induction slag melting of radioactive waste.
Creation of New Fuel Elements Generation for Water-Cooled Power Reactors of Different Purposes.
Development of Decontamination Techniques and Technologies for Industrial Buildings and Equipment that are Polluted by Radionuclides
#0220Fast Sodium Reactors
Studies of Physics and Engineering Problems for Safety Increase and Burning of Actinides Efficiency for Advanced Fast Reactors.
Development of Surface Decontamination Methods based on Using Foams and Microheterogeneous Suspension.
Automatic Television Analyzer Development for Industrial Microstructure Control of the Fuel Tablets (ATLANT-TT).
Development of a Sophisticated Computer Based Data System for Evaluation of the Radiation Legacy of the Former USSR and Setting Priorities on Remediation and Prevention Policy.
Investigation of the Radiation in Nuclear Fuel Cycle Based on Reprocessed Uranium and Mixed Uranium-Plutonium Fuel.
Development of Scientific Fundamentals for Active Waste Minimization in Extraction Spent Nuclear Fuel (SNF) Reprocessing.
Process Development for Utilization of Civil and Military Plutonium in Fast and Thermal Reactors with Account for Ecology and Economics Requirements
Development of Tritium Targets for Small-dimension Sealed Neutron tubes with High Reliability ("INTEGRITY").
Development of Technology to Remove Transuranium Elements from Silt of Radioactive Storage Ponds.
A Safe Method for Storing Large Masses of Plutonium and Uranium after Dismount of Nuclear Weapons.
#0332-2Safe U and Pu Storage
Project for the Safe Storage of large Masses of Weapon-grade Plutonium and Uranium
Ecological Pure Antibiotics Production.
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.
Study on the Feasibility and Economics of the Use of Ex-Weapons Plutonium and Civil Plutonium as Fuel for both Fast and Thermal Reactors.
Research on the Process of Liquid High-Level Waste Solidification in Induction Smelter with Cold Crucible.
Development and Creation of New Forms of Ophthalmology b - Applicators for Radiation Therapy of Eye Cancer and Study of Psycho-Physiological Effects on Man of Low Frequency Electromagnetic Radiation Emitted by Radio Nuclides.
Investigation of non-thermal Possibilities of Origin of the Superconductivity in High-Energy Pulsed High-gamma-neutron Fluxed.
Development of Biological Methods for Recultivation of Soils Polluted with Radionuclides.
Molecular Design of Extractants to Resolve Tasks Relevant to Ecology and NPP Spent Nuclear Fuel Reprocessing.
#0486First Wall Materials
Investigation of Structure and Mechanical Properties of Perspective Structural Materials for the First Wall of the Thermonuclear Reactor after the exposure of Ion Beams, Plasma Radiation of Laser Range and Dynamic Loads Modeling the Plasma Attack...
Physicochemical Studies of Basalt Materials and Ceramic Chromite-Niobate Composites for the Purpose of the Immobilization of Ecologically Hazardous Actinides and the Making of Protective Barriers for a Long-term Safe Storage of Radwastes.
#0523Cutting of NPP Parts
Research of the Cutting Methods During Withdrawal of NPP from Operation.
Complex Investigation of Uranium Dioxide and Mixed Uranium-Plutonium Dioxide Fuel's Properties for Prediction of Performance and Operating Characteristics and Verification of Calculating Models of Fuel elements for Operative and Advanced NPP.
#0534.2Uranium Dioxide Properties
Investigation Properties of Uranium Dioxide Advanced and Mixed Uranium-Plutonium fuels (MOX) for Prediction of Performance and Operating Characteristics to Provide Certification Fuel and Verification of Computational Models for Parameters Definition of Ox
#0538Packing Nuclear Fuel
Development of Scientific Foundations of the Technology of the Metal Matrix Packing of Leaky Unreprocessible Spent Nuclear Fuel of Different Purpose Reactors for a Long-term Environmentally Safe Storage.
Study of Structure of Materials Based on U-Pu-Zr alloy, their Thermodynamic Properties and Interaction with Materials of Fuel Element Shell under Quasi-Isothermal Conditions and Conditions of Non-stationary Exposure
Creation of Superconductors Applicable to Magnetic Systems of the Large Hadron Collider (LHC, CERN).
Developing Confinement Techniques for Radioactive Matters within Topsoil to Prevent their Spread with Water and Wind from the Sites on Nuclear Fuel Cycle Sites.
Fundamental Research of Materials Structure and Properties Changes Resulted from Irradiation by Means of Complex of Modern Physical Methods
Working out Educational and Methodological Base and Technical Means for Federal Training Center in the Field of Radioactive Waste Management
Specialized Mass Spectrometers for Analysis Tritium Gas Mixed in "In-line" Mode
Development, Fabrication and Test of a Superconducting Quadrupole magnet with High Gradient (200 T/M) and Large Aperture (7 CM), Based on Nb3Sn Superconductor
In-Pile Tests of New Generation Fuels for VVERs of Different Purpose
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 Quality Control of Magnatic Powders aand Permanent Magnets Prodused with Use of Technology and Equipment Formerly Applied for the Manufacturing of Nuclear Weapons
The Quality Control of Magnetic Powders and Permanent Magnets Produced with use of a Technology and Equipment Formerly Applied for the Manufacturing of Nuclear Weapons
Study of Gas- and Molten-Fluoride Separation and Transmutation for Accelerator Based Plutonium Disposition and Nuclear Waste Treatment
#0771MOX Fuel Fabrication
Development of Pulsed and Vibration Nuclear Power Reactor MOX Fuel Fabrication Equipment
Development of a Super-Intensive Pulsed Neutron Source for Physics Research RIN-10 on the Basis of the INR RAS Accelerator-Storage System
Mastering the Process and Equipment for Induction-Slag Melting High Activity Level Metal Wastes
Creation of a Database for Computational Codes, Realizing Detailed Mathematical Modeling of a Radioactive Fission Products Realize from Fuel Rods VVER 440, VVER 1000
Development of a Technical Design for DU-shielded Transport Cask with Increased Spent Nuclear Fuel Specific Loading
#0967Gallium in MOX Fuel
Studies of the Influence of Ga Available in Weapons Grade Plutonium on the Quality of Produced Fuel and Serviceability of Fuel Rods
Fluctuation Phenomena in Transition Metal and Actinide Based Systems with Magnetic and Structural Instabilities
Development of Scientific Basis for Decontamination of Soils, Contaminated as a Result of Chernobyl Accident
Development of Technological Options for Fission Platinoid Recovery from Spent Nuclear Materials
Development of Scientific Fundamentals for Development of Low-Activation Radiation - and Corrosion-Resistant Vanadium-Based Alloys to be Used as Structural Materials for the first Wall and Tritium Blanket Thermonuclear Fusion Installations and Reactors
Search for Electron Antineutrino Rest Mass in the Tritium b-decay
Development of Fabrication Technology and Studies into the Properties of Fuel Materials Containing Skeleton-Type Inert Diluent (Without U-238) to Utilize Weapon Grade and Civil Pu as well as Minor Actinides (Np, Am, Cm, etc.) in Power Reactors With Improv
Development of the Technology for Partitioning of Radioactive Waste Arising in Spent Nuclear Fuel Reprocessing
Development of Technology for Metal Surface Decontamination in Aqueous Solutions
Validation of Technical Feasibility of Burning Weapon's Grade and Civil PU Via New Generation PWR Fuel Elements Designed in ISTC Project N173-95
New Materials for Surgery
Development of Scientific Bases and Technological Aspects of Creation of New Generation Hard Deformation of Cr-Ni Staainless Steels with the High Contents Boron (1,0-1,9% of Weights) on the Basis of Principles of Metallurgy of Atomized Powders of an Alloy
Development of Multiaimed Low-Waste Technology of Production of Spherical Aluminium Oxide and Catalysts and Adsorbents on its Base which Allows to Solve Urgent Ecological Problems in Various Branches of Industry
Investigation of the Radiation in Nuclear Fuel Cycle Based on Reprocessed Uranium and Mixed Uranium-Plutonium Fuel
Development of a Nuclear Materials Control and Accounting System Model for Complex Nuclear Facilities
Development of Technology for Fire and Explosion Safe Storage of Wastes from Industrial Processing of Metallic Uranium
Use of Coherent and Non-linear Acoustic Methods in Nondestructive Testing and Seismology
Study of Metal Tritides
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
Investigation of the Effect of Exposure to Tritium and Reactor Irradiation on the Properties of the First Wall and Divertor Materials for Magnetic Fusion Experiment
Evaluated Data Exchange Properties of Substances and Materials Utilized and Produced by Nuclear Industry
New Materials for a Micro-Filtration
Use of IPEC for Remediated Soils Contaminated from Nuclear and Industrial Activities
Mastering Technology and Equipment Based on Induction Melters with “Cold” Crucible for conditioning Active Metal Waste and Thermal Insulation Materials Arising at Operating and Decommissioned NPP and Radiochemical Plants to Storage and final Disposal
Method Development of Essential Increase of Gamma-Resonant Spectroscopy Resolving Power and of New Type Gamma-Sources Design for Use in This Field
Development of the Technology to Obtain Pure Metal Scandium by Thermal Decomposition of Scandium Iodide
New Composite Multifunctional Coatings Produced Using SHS-Electrodes
Metal Matrix Composites on the Basis of Nano-Materials
Supercritical Fluids – Basis of Fundamentally New Technologies of Radioactive Waste Conversion
Perspective Materials for Brickwork Elements of External Catchers of Operating and Design NPP. Methods of Severe Accidents Consequences Mitigation
Low Enrichment Uranium Core for Floating Nuclear Power Plant Reactor (FNPP) as a way of Resolving Weapon’s Nuclear Material Nonproliferation Problem
Improvement in Environmental Safety of Irradiated Material Extraction Reprocessing
Development of Scientific Fundamentals for Creation of Irradiation Resistant Structural Zr Alloys for Nuclear Reactor Cores
The Study of the Immobilization of Pu, Sr+Cs and Rare-Earth Element Waste Fractions from Spent Nuclear Fuel and Weapon Materials Reprocessing
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
Nuclear Safe Ceramics for Compact Storage and Immobilization of Plutonium and Nuclear Power Engineering Actinide-Containing Wastes
Optimization of the Technology of Steel Casting Reinforcement by Hard Alloys with the Use of Computer Modeling
The Exploration of the Immobilization Method of Alpha-Active Wastes in Chemically Stable Porous Composites
Development of the Method for Characterization of the Samples, Containing Spontaneously Fissioning Radionuclides, by Measuring Fission Products Gamma-Radiation (for the System of NM Control and Accountability of the Federal State Unitarian Enterprise "PA"
Composite Materials with Nano-Scale Reinforcements
Methods of Improvement of Drawability of Automobile Sheet from IF-steel
Synthesis of Sorbents of the New Type and Development of the Sorbent-Based High Performance Technologies for Decontamination of Water from Chemical and Radioactive Contaminants
Study of Affecting of Gamma-Radiation on Polymeric Solutions and their Component for Deriving Paint Coatings with New Service Properties in Operation Conditions of Atomic Productions and NPP
MATINE - Study of Minor Actinide Transmutation in Nitrides: Modelling and Measurements of Out-of-pile Properties
Development of a Comprehensive Decontamination Database and an Absorption-Electrochemical Metal Surface Decontamination Technique Combining Chemical and Electrochemical Process
Production and Testing of Heavy Concretes Including Depleted Uranium Dioxide Concerning their Use as Shielding Materials in Constructions of Casks for Spent Nuclear Fuel
Production and Testing of Cast Cermet on the Base of Stainless Steel and Depleted Uranium Dioxide as Applied to its Use as Shielding Materials in Constructions of Casks for Spent Nuclear Fuel and Radioactive Wastes
Creation of a Database on Electromagnetic, Mechanical, and Thermal Parameters of Superconducting Nb3Sn Composite Strands and Components of Composite Strands
Development of Express and High-Sensitive Liquid Scintillation Alpha-Spectrometric Method of Determining Actinides in Process Solutions from Radiochemical and Isotope Production and in Environmental Samples
Problem of Search for the Neutrino Mass in the Cosmologically Important Sub-Electronvolt Region by Means of Tritium Beta Decay Spectrum Measurement. Study of the Systematic Effects in New Proposed Experiment KATRIN with Existing Set-up “Troitsk Neutrino-M
A Profound Study of Non-Dendritic Solidification Mechanisms at Ultrasonic Cavitation Effect upon the Melt for Obtaining Ultimate Refined Structure in Light Alloy Ingots
Experimental Investigation and Mathematical Modeling of Radiation-Chemical Processes in the PuO2 – sorbed Water System
Research of Characteristics and Dynamics of Exothermic Reaction Runaway of Nitric Acid with Organic Compounds in Heterogeneous Systems
Development of Acoustical Detection Methods for Ecological Monitoring
Development of the Scaled Methods for Depositing Heteroepitaxial Doped Diamond Films. Creation and Investigation of Devices Based on the Films
Development and Testing of the Express Method and Analytic Equipment for Early Diagnosis of Cancer Diseases Taking into Account the Radiation Factor
Develop a Transport Cask for Transportation, Storage and Burial of Spent Nuclear Fuel and Radioactive Waste Using Cast CERMET Based on Dioxide of Depleted Uranium and Steel
Experimental Validation of IFMIF Lithium Target Long-Term Performance
Fabrication of Experimental CANDU MOX Fuel Pins for Irradiation Testing in the MIR Reactor
MATINE 2- Study of Minor Actinide Transmutation in INErt Matrices Fuels: Modeling, Fabrication and Measurements of Out-of-Pile Properties
Investigation of Up-to-Date Mass Spectrometer Method Сapabilities to Determine Isotopic Ratio of Stable Elements During Criminalistic Examinations on Seized or Withdrawn Materials
Production and Testing of High-strength Concretes Including Depleted Uranium Dioxide Concerning their Use as Shielding Materials in Construction of Casks for Spent Nuclear Fuel. Stage 2
Development of the Concept on Improving the Normative and Legal Regulation on Combating Illicit Trafficking of Nuclear and Radioactive Material in the Russian Federation
Fire Retardand /Heat Resistant Paint, Primer Insulation and Other Materials
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.