Reactor Pumped Laser for ICF Feasibility
Designing of the Specialized Small-Sized Medical Reactor for Neutron- and Neutron-Capture Therapy
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.
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
Development of a Super-Intensive Pulsed Neutron Source for Physics Research RIN-10 on the Basis of the INR RAS Accelerator-Storage System
Experimental Substantiation of Technology for Molybdanium-99 Extraction from Fuel Solution of Fluid-fuel Reactor and Design Development of the Medical Isotope Production Complex
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
Development of Production Technologies of High Pure Radioactive Isotopes for Medical and Biological Application on the Base of the Research fast Neutrons Reactor
Creation of a Database for Computational Codes, Realizing Detailed Mathematical Modeling of a Radioactive Fission Products Realize from Fuel Rods VVER 440, VVER 1000
Thermovision System for Control of Nuclear Power Plant's (NPP) Equipment
Measurement and Evaluation of the Thorium Fuel Cycle Neutron Data
Complex Calculation and Experimental Research to Select the Optimal Composition and Application Mode of Ophthalmic Applicators for Treatment of Eye Cancer
Level Density Studies Based on Measurements of Evaporation Spectra and Cross-Section Fluctuations in Nuclear Reactions
Feasibility Study for the Creation of a Neutron Therapy Centre on the Basis of Nuclear Reactors
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
Development of Ceramic Composite Materials and Structural Elements for High-Temperature Nuclear Reactors
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
Developing a Computer-Based Terminology Glossary Covering Inregrated Approach to Non-Reactor Nuclear Materials Safety Management
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 and Creation of Radioactive Targets on the Basis of Russian Nuclear Technologies
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.