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#0487Self-Quenching Pulse Reactor

Development and Computational-Experimental Validation of the Concept of Self-Quenching Multi-channel Pulse Graphite Reactor (MIGR) for the Studies on Nuclear Reactor Safety.

#0517Skyshine Shielding Experiments

Experimental Studies of Reactor Radiation Scattering in the Atmosphere.

#0709Rock Materials at Waste Disposal Sites

Experimental and Theoretical Studies on the Influence of Fluids on the Structural and Physiological Mechanical Properties of Rick Materials in Nuclear Waste Burial Sites

#3705Electronic Seals

Examination of Functional Capabilities of Electronic Seals at the RFNC VNIITF, Enterprises of the Ural Region, and NNC of the Republic of Kazakhstan

#3824Diagnostics for Tokamak Divertor Plasma

Research and Development of Advanced Diagnostics for Divertor Plasma in the KTM Tokamak

#K-040Technology for Production of Beryllium Materials and Coatings

Technology for Production of Beryllium Materials and Coatings and Investigation of Its Properties at the Conditions Simulating the Temperature-strength, Gaseous and Radiation Effects of TNR.

#K-040.2Technology for Production of Beryllium Materials and Coatings

Technology for Production of Beryllium Materials and Coatings and Investigation of Its Properties at the Conditions Simulating the Temperature-strength, Gaseous and Radiation Effects of TNR.

#K-040.3Technology for Production of Beryllium Materials and Coatings

Technology for Production of Beryllium Materials and Coatings and Investigation of Its Properties at the Conditions Simulating the Temperature-strength, Gaseous and Radiation Effects of TNR.

#K-048Reactor Facility Decommissioning

The Development of Decommissioning of Operation Technology of the Reactor Facility with Research RA Reactor of the Institute of Atomic Energy of the National Nuclear Center of the Republic of Kazakhstan.

#K-057Nuclear Materials Storage

Creation of System for Storage, Operative Control and Physical Protection of Nuclear Materials and Ampoule Sources of Ionizing Radiation (ASIR) on "Baikal-1" stand Complex Meeting the International Requirements of Radioactive Materials Control...

#K-1006Off-Gas Purification System for BN-350 Reactor Sodium Processing Facility

Upgrade of the Off-Gas System for the BN-350 Reactor Sodium Coolant Processing Facility

#K-106Removal of Nuclear Materials to Russia

Preparation of Removal of Nuclear Fissile Materials, Belonged to RF and Located on the Territory of the Institute of Atomic Energy of the National Nuclear Center of the Republic of Kazakstan, to the Russian Federation

#K-1265IN-VEssel COrium Retention (INVECOR) in accident of water reactor

Experimental Study of the Processes at the Corium Melt Retention in the Reactor Pressure Vessel

#K-1329ITER First Wall in Accident

Simulation of ITER First Wall Behavior in Accident Conditions Caused by Cooling System Failures

#K-1391Atomic Lake at Semipalatinsk Test Site

Integrated Assessment of “Atomic Lake” Condition Influence on Ecosystem of the Region

#K-1566Purification of Irradiated Beryllium

Recycling Technology of Irradiated Beryllium

#K-1797Fuel for High Temperature Gas Cooled Reactor

Investigation of HTGR Fuel Performance in WWR-K Research Reactor

#K-1863Beryllium-Hydrogen Interaction

Studies of Beryllium-Hydrogen Isotopes Interaction under Reactor Irradiation

#K-223Decontamination of Stainless Steel

Decontamination of Radioactive Stainless Steel by Electroslag Remelting

#K-527Radiation Heating of Structural Materials

Verification of the Method for Computation of Radiation Heating of Structural Materials at Research Reactors (Based on Results of Computational and Experimental Investigations at IGR Reactor)

#K-578Lithium Ceramics for Thermonuclear Reactor

High Li-burnup Irradiation Tests of Ceramic Tritium Breeder

#K-883Corrosion Resistance of Radwaste Storage

Corrosion Protection Experimental Studies and Tests under Gamma-Radiation and Heating Combined Effect in BN-350 Spent Fuel Dry Long-Term Storage Facility Silo Models

#K-970Development of Technology of Sodium Hydroxide Processing into Geocement Stone

Development of Experimental-Industrial Technology of Radioactive Waste Processing into Geocement Stone and Equipment for its Realization

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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