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#0017Plutonium Conversion

Feasibility study of technologies for accelerator based conversion of military plutonium and long-lived radioactive waste.

#0018Reactor Pumped Laser for ICF

Reactor Pumped Laser for ICF Feasibility

#0040Nuclear Materials Accounting

System design for safeguarding nuclear materials utilized at complex nuclear facilities.

#0085Radiation Ambient Monitoring

ISTC Environmental radiation ambient monitoring system.

#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.

#0153-2Thermovision Monitors for Nuclear Reactors

Thermovision System for Control of Nuclear Power Plant's (NPP) Equipment

#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.

#0220Fast Sodium Reactors

Studies of Physics and Engineering Problems for Safety Increase and Burning of Actinides Efficiency for Advanced Fast Reactors.

#0304Accelerator-Based Measurements of Minor Actinides Cross-Sections

Measurements and Analysis of Basic Nuclear Data for Minor Actinides

#0336Reactor for Neutron Therapy

Designing of the Specialized Small-Sized Medical Reactor for Neutron- and Neutron-Capture Therapy

#0369Economics of Plutonium Burn

Study on the Feasibility and Economics of the Use of Ex-Weapons Plutonium and Civil Plutonium as Fuel for both Fast and Thermal Reactors.

#0371Pu-Utilization in LWR Experiments

Critical Experiments for the Pu- Utilization in LWR Type Reactors Using IPPE Facilities.

#0371-2Pu-Utilization in LWR Experiments

Critical Experiments for the Pu Utilization in VVER Type Reactors Using IPPE Facilities. (Phase 2-Basing of Three VVER FAs loading. Pre-SUPR Experimental Program)

#0559Lead-Bismuth Target

Pilot Flow Lead-bismuth Target of MW Power for Accelerator-Driven Systems

#0564Temperature of Water-cooled Reactor

Methodological Security of Temperature Measurement and Diagnostics within Power Water-moderated Water-cooled Reactor (PWR) Type on Base of Analysis of Influence Functions for Measuring Means.

#0650Safety of Advanced Fast Reactors

Study on the Physical and Engineering Problems Concerning the Increase in Safety and Actinides Burning Efficiency of Advanced Fast Reactor

#0723-2Recycling Weapon-grade U and Pu in U-Th Closed-cycle Reactors

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

#0731Benchmark Data on Gamma-ray Production for Fusion Reactors

Benchmark Data on Gamma-ray Production for Evaluated Data Testing for Fusion Application

#0733Al Oxide Aerogel Production

Physico-Chemical Bases of Aluminium Oxide Aerogel Synthesis and Development of Continuous Technology for its Production from a Ga-Al Liquid Metal System

#0777Production of Radionuclides and Radiopharmaceuticals

Development of Research Methods for WWR-c Nuclear Reactor Application in the Chemistry and Ecologically Sound Technology for Production of Radionuclides and Radionuclide-Based Organ-Selective Radiopharmaceuticals

#0779Dismantling of BR-10 Fast Reactor

Development of Technology of the BR-10 Reactor Dismantling and Radioactive Wastes Processing Before Utilization

#0815.2Codes for Nuclear Safety Evaluation

Development of Computerized Technology for Critically Safety Uncertainty Evaluation based on the Analysis of Data for the International Bank for Critical Experiments

#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

#0828Molybdenium Extraction from Reactor Fuel

Experimental Substantiation of Technology for Molybdanium-99 Extraction from Fuel Solution of Fluid-fuel Reactor and Design Development of the Medical Isotope Production Complex

#0910Nuclear Data of Vanadium

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

#0910.2Nuclear Data for Vanadium

Execution of the Complex of Benchmark-Experiments for Testing the Nuclear Data of Vanadium - Main Component of Low-Activation Structural Materials for Advanced Nuclear Energy

#0916High Pure Radioisotopes

Development of Production Technologies of High Pure Radioactive Isotopes for Medical and Biological Application on the Base of the Research fast Neutrons Reactor

#0941Database on Fission Products Release

Creation of a Database for Computational Codes, Realizing Detailed Mathematical Modeling of a Radioactive Fission Products Realize from Fuel Rods VVER 440, VVER 1000

#0962Alpha-Emitting Radionuclides for Medicine

Development of Extraction and Deep Purification Technologies of Alpha-Emitting Radionuclides for Medical Application

#0969Neutron Data for Thorium Cycle

Measurement and Evaluation of the Thorium Fuel Cycle Neutron Data

#1002Treatment of Eye Cancer

Complex Calculation and Experimental Research to Select the Optimal Composition and Application Mode of Ophthalmic Applicators for Treatment of Eye Cancer

#1015Environmental Impact of Fuel Cycles with Plutonium

Evaluation and Prognosis of radiological and Ecological Effects of Nuclear Fuel Cycles in Russia when Using Weapons- and Power- Grade Plutonium, and Definitions of Ways to Reduce These Effects

#1049Nuclear Level Density Studies

Level Density Studies Based on Measurements of Evaporation Spectra and Cross-Section Fluctuations in Nuclear Reactions

#1059Neutron Therapy

Feasibility Study for the Creation of a Neutron Therapy Centre on the Basis of Nuclear Reactors

#1070Low-Radiation Vanadium-Based Alloys

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

#1097SIC/SIC Composite

Irradiation Creep of SiC/SiC Composites. Stage 1. Development of Method and Test Facility Modernization for SiC/SiC Composites In-reactor Testing.

#1130Ceramic Composite Materials

Development of Ceramic Composite Materials and Structural Elements for High-Temperature Nuclear Reactors

#1143Terminology Glossary for Nuclear Material Safety

Developing a Computer-Based Terminology Glossary Covering Inregrated Approach to Non-Reactor Nuclear Materials Safety Management

#1193Fuel Materials with Non-Uranium Diluent

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

#1246Nondestructive Burnup Measurements

Nondestructive Control of a Burnup Depth of Spent Fuel for RBMK-1000 Reactors in Storage Pond of Nuclear Power Plants

#1321ROX-Fuel Fabrication

Development of Technology of ROX-Fuel Fabrication and Analysis of Characteristics of Nuclear Reactors Using ROX-Fuel

#1345Radioactive Targets

Development and Creation of Radioactive Targets on the Basis of Russian Nuclear Technologies

#1346Microbial Conditions in Spacecraft

Investigation on Means and Methods for Controlling the Microbial Conditions in Manned Modules of Long-Operating Space Vehicle

#1347Lithium Detector of Solar Neutrinos

Development of Lithium Detector of Solar Neutrinos on a Basis of Prototype with 300 kgs of Lithium

#1356Model for Nuclear Materials Control and Accounting

Development of a Nuclear Materials Control and Accounting System Model for Complex Nuclear Facilities

#1372Transmutation Effectiveness of Nuclear Waste

Complex Radiochemical and Activation Analysis of Long-life Nuclear Waste Transmutation in Fast Reactors and in the Beams of High Energy Accelerators

#1405Proton Induced Fission Cross Sections

Proton Induced Fission Cross Sections for Heavy Nuclei in the Energy Range 200-1000 MeV

#1411Simulation of Reactor Core Accidents

Experimental and Numerical Study of Liquid Metal Boiling as Simulation of Accidents in fast Reactor Core

#1431Intensive Neutrino Source

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

#1443Plutonium Utilization Scenarios

System Analysis of Weapons and Civil Plutonium Utilization Scenarios in the Nuclear Fuel Cycle of Russia Taking into Account Economics, Non-Proliferation and Ecology Factors

#1484Accelerator Source for Neutron Therapy

Accelerator Based Neutron Source for the Neutron-Capture and Fast Neutron Therapy

#1537ISO Compatible Product Data Base

Elaboration of Software Package for Product Data Management System During Product Life Cycle Meeting Requirements of ISO 10303 STEP

#1595Sorption Membranes for Waste Solidification

The Development of Nonconventional Sorption - Membrane Technology of Rendering Liquid R/A Wastes from NPP and Nuclear Submarines Harmless and Solidifying Them into Water - Resistant Mineral Geocement Stone

#1596Aluminium Industry Waste Reprocessing

Development of Complex Technology for Reprocessing Aluminium Industry Harmful Waste with Separation of High-Pure Gallium and Copper Accompanying Products

#1611Thermohydraulics in Liquid Metal Cooled Reactors

Generalisation of Data on Hydrodynamics and Heat/Mass Transfer Processes in Liquid Metal Cooled Reactors

#1749Fission Cross Sections for Minor Actinides

Measurements of the Cross Sections of Fast and Resonance Neutrons Induced Fission of Minor Actinides for Their Transmutation with Accelerator-Driven Systems

#1755Experimental Modeling of Accelerator - Blanket System

Experimental Study of Fast and Fast-Thermal Accelerator Driven Systems on the Basis of BFS-1 – Microtron Complex

#1767Liquid Metal Coolant Disposal

Development of Components and Design Specification on the Facilities for Conversion into Safe Condition of the BR-10 Reactor Liquid Metal Coolant Radwaste and Related Section of the Reactor Decomissioning Project

#1796Nuclear Data for Astrophysics

An Extended Data Base of the Beta-Decay Properties and Nuclear Reaction Rated for Astrophysical Applications

#1821Monograph on Coupled Pulsed Reactor Systems

Preparation of the Scientific Monograph "Coupled Pulsed Reactor Systems"

#1857Informational Technologies for Export Control System

Telecommunication Informational and Analytical System for Technical Support of Export Control for MINATOM of Russia

#1886Endurance of Accelerator Beam Window

Investigations of the Irradiation and Thermomechanical Endurance of the Beam Window of ADS Neutron Generating Target

#1931Oxide Nanoparticles in Lead Melt

Development of Technology for Production of Nanodimensional Oxide Materials in Lead Melt for New Microsystem Method of Forming Sensitive Layers of Semiconductor Gas Sensors

#1954Fissile Materials Identification Device

Development of the Technology for Prompt Control and Identification of Uranium and Plutonium in Containers with Application of a Non-Destructive Method on the Basis of a Russian Portable Rapid Inventory Confirmation System

#1969Neutron Therapy at the Nuclear Reactors

A Characteristics Optimization of the Neutron Beams of the Nuclear Reactors and Clinical Basis for Their Application in Neutron Therapy

#2025Radiation Sources for Brachytherapy

Complex Research and Development of Sealed Therapeutic Radiation Sources with Optimal Medical, Technical, and Economic Parameters

#2036Lithium Circulation Loop and Lithium Neutron Target

The Thermal-Hydraulic and Technological Investigations for Validation of the Project of Lithium Circulation Loop and Neutron Lithium Target for IFMIF

#2048Improvement of Steels Corrosion Resistance

Improvement of Corrosion Resistance of Constructional Steels in Liquid Pb and Pb-Bi Alloys by Means of Their Surface Modification with the Help of Pulsed Electron Beams and Protective Coatings

#2199Neutron Cross-Sections and Level Density for Fission-Products, Th, 233-U

Neutron Cross-Sections in Resonance Energy Range and Nuclear Level Density for Fission-Products, Th, 233-U

#2253Investigation of the Delayed Neutron Characteristics

Investigation of the Delayed Neutron Characteristics from the Fission of Compound Nuclei Th-233, U-234, U-235, Am-244, Np-238, Cm-246, Pa-233, Pa-234, Np-239, Np-240 at the Excitation Energies from 5 to 20 МeV

#2253.2Investigation of the Delayed Neutron Characteristics

Investigation of the Delayed Neutron Characteristics from the Fission of Compound Nuclei Th-233, U-234, U-235, Am-244, Np-238, Cm-246, Pa-233, Pa-234, Np-239, Np-240 at the Excitation Energies from 5 to 20 MeV

#2306Rectifier on a Heat-into-Electricity Thermionic Converter Basis

Creating the High Current Low Voltage Rectifier on a TEC Basis (TEC-Rectifier)

#2569Neutron Source for Boron Neutron Capture Therapy

Accelerator Based Neutron Source for Boron Neutron Capture Therapy

#2573Laser Separation of Lead Isotopes

Investigation of Processes of High - Performance Laser Separation of Lead Isotopes by Selective for Development of Environmentally Clean Perspective Power Reactor Facilities

#2582Actinides Transmutation Study at Critical Assembly

Experimental Study of Minor Actinides Transmutation Problem at BFS-73-1 Fast Critical Assembly

#2603A Database of Critical Experiments

Development of a Database on Description of BFS and KOBR Critical Experiments and Their Interfacing with Analytical Tools

#2607Scission Neutrons in Low Energy Fission

Experimental Search and Study of Scission Neutrons in Low Energy Fission

#2650High Activity Generator for Radiotherapy

Development of High Activity Stationary Medical Generator of W-188/Re-188 and Cold Kits to the Generator for Radiotherapy on the Basis of Re-188 Eluate

#2659Optical Fibers under Irradiation

Effects Induced by Pulsed and Steady-State Irradiation of Silica Core Fiber Waveguides

#2661Reactors with Lead Сoolant

Analytical and Experimental Substantiation of Neutron-Physical Characteristics of Fast Reactors with Lead Coolant

#2680Minor Actinide Transmutation in Nitrides Fuel Environment

MATINE - Study of Minor Actinide Transmutation in Nitrides: Modelling and Measurements of Out-of-pile Properties

#2689Supercritical Pressure Water for Nuclear Power Engineering

Assessment of the Potentialities of the Use of Supercritical Pressure Water for Nuclear Power Engineering

#2695Bi-213 Generator for Radiotherapy

Development of Ac-225/Bi-213 Generator and Radiopharmaceuticals on the Basis of Bi-213 Eluate for Radiotherapy

#2698Tungsten Nuclear Data

Evaluation and Integral Validation of Nuclear Data of Tungsten – Candidate Material of Fusion Reactor Diverter

#2711Neutron Induced Total Fission Cross Sections

Measurement of Neutron Induced Fission Cross Sections for 238U, 232Th, 209Bi, natPb, 197Au and natW in the Energy Range 20-175 MeV

#2769Aggregation of Shungite Carbon Nanoparticles

Complex Investigation of Aggregation of Carbon Nanoparticles and Their Role as Basic Elements of Nanotechnology in Systems: Shungites, Aqueous Dispersions of Shungites

#2786Radionuclide Migration in Polluted Areas

Quantitative Assessment of Soil Particles-Bound Radionuclides Redistribution in Landscapes and Prediction of Their Environmental Behaviour (the Case Study in the Chernobyl Caesium Hotspot, Plavsk, Tula Region, Russia)

#2787Moderators for Pulsed Neutron Source

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

#2862Low Dose Radiation Effect on Cancer Risk

Analysis of Dose-Response Relationship for Cancer Occurrence among Workers of Nuclear Industry of the Russian Federation: Solving the Problem on the Radiation-Epidemiological and Molecular-Genetic Approach-Based Prediction of Individual Risk

#2884Minor Actinides Cross-Sections

Integral Experiments at BFS Critical Facilities for Justification of Minor Actinides Transmutation and Their Analysis

#2911Power Fast Reactor Radioactive Sodium

Development of Technology of Conversion to the Safe Condition of Non-Drained Residues of Sodium Radwaste in Fast Reactors

#2918Civilian Nuclear Power Technology and Nuclear Weapons Proliferation

Development of Concept and Methodology for Assessing Risk of Nuclear Weapon Proliferation through Civilian Nuclear Power Systems

#2979Local Radiofrequency Hyperthermia

Development of Techniques for Local RF Hyperthermia Delivered to Deeply Located Malignant Tumors in Patients with High Body Mass

#3020Control of Oxygen Content in Lead Coolants

Development of Oxygen Sensors, Systems of Control of Oxygen Content in Lead Coolants for Test Loops and Facilities

#3031Conditioning Middle-Active Liquid Wastes into Matrix

Development of Resource Saving Alternative Technology of Conditioning Nuclear Power Plant Middle-Active Liquid Wastes with High Salt Content into Water Stable Mechanically Strong Isolating Matrix

#3041Graphite Isotope Ratio Method

Verification of Graphite Isotope Ratio Method to Restore Neutron Local Fluence in Reactor Core with Graphite Moderator by the Example of the Reactor of the First A-Plant in Obninsk to Control Non-Proliferation of Nuclear Fissile Materials

#3069Perturbation Theory in the Nuclear Power

Preparation of the Scientific Monograph "Perturbation Theory and Adjoint Function Method in the Problems of Nuclear Power"

#3094Control of subcriticality of neutron multiplying systems

Development of experimental Prototype of Equipment and Measuring Technique for Control of Subcriticality of Neutron Multiplying Systems

#3099Purification of Sodium Coolant

Generalization of the Experience of Investigations on Maintenance of Sodium Coolant Purity

#3239Experiments for Lead Cooled Reactors

Benchmark Experiments At BFS Facilities For Pb (Pb-Bi) Critical Media Integral Parameters Testing

#3297Targets for Neutron-Rich Nuclei Investigation

Development and Creation of Radioactive Ве-10 Targets on the Basis of Russian Nuclear Technologies

#3354Lithium Target for International Fusion Materials Irradiation Facility

Experimental Validation of IFMIF Lithium Target Long-Term Performance

#3392Microbiological Safety of Space Equipment

Development of Means and Methods to Ensure Microbiological Safety of Long-Operating Space Equipment

#3437Pulse Generator for Cancer Treatment

The Development of Methods and Apparatus for Cancerous Growth Diagnostics and Therapy on the Base of Neutron and X-Ray Radiation Pulse Generator

#3544Validation of Neutron Data of Structural Materials

Validation of Files of Estimated Neutron Data of Structural Materials (Stainless Steel, Iron, Nickel, Chromium and Zirconium) based on Integral Experiments

#3608Minor Actinide Transmutation in Inert Matrices Fuels

MATINE 2- Study of Minor Actinide Transmutation in INErt Matrices Fuels: Modeling, Fabrication and Measurements of Out-of-Pile Properties

#3679Hydrogen Production

Development of Hydrogen Production Technology Based on Direct Contact of Water, Gaseous Hydrocarbons and Their Mixtures with Liquid Pb and Pb-Bi

#3698Radiation Sources for Therapy of Tumors

Development of Sealed Radiation Sources for Therapy of Malignant Tumors in the Vision Organ

#3760Immobilization of High-Level Wastes

Immobilization of High-Level Wastes in Resistant Mineral-Like Materials in the Self-Propagating High Temperature Synthesis (SHS) Mode

#3891Biomimetics for Detection of Air Pollutants

Intelligent Multifunctional Biomimetics for Optical Nanodevices: New Materials for Environment Protection

#4026Thermionic Converter Based Rectifier

Creation of a High-Current Low-Voltage Thermionic Rectifier with the Phase Control of the Output Voltage

#A-1209Geocement binding materials for radioactive waste immobilization

Development of New Types of Geocement Binding Materials Based on Natural Minerals and Technology of Conditioning of Radioactive Absorbents (Zeolites) and Sludge Immobilized in Geocement Matrix

#A-1749Geocement Binders for Liquid Radioactive Waste

Development of New Geocement Binders Based on Natural Minerals of Armenia and Technology of LRW Conditioning into Ecologically Safe Compounds

#B-175Conception of Light Water Reactors

Methodical and Calculated Substantiation of the Conception of Light Water Reactors with a High Level of Reactivity Self-compensation and Critically Safety for a New Generation of Nuclear Low-power Plants

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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