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#K-1041Divertor and Transport System for Fusion Device

Divertor and Transport System for Fusion Devices

#K-1125Database for Semipalatinsk Test Site

Creation of a Comprehensive Database of the Former Semipalatinsk Test Site

#K-1328Semipalatinsk Test Site Contamination

Semipalatinsk Test Site Environment Assessment Using Bioindication Methods

#K-1561Tokamak Divertor on the Base of Lithium

Development and Manufacturing of Demonstration Models of KTM Tokamak Divertor In-Vessel Plasma Facing Elements on the Base of Liquid Lithium

#K-2204Lithium. Tritium.

Reactor Studies of Lithium CPS

#K-234Radiological Safety at Former Nuclear Explosion Sites

Estimation of Radiological Safety on Sites of Series of Technological Peaceful Nuclear Explosions in Kazakhstan

#K-2374Methodology for activity planning at technogenic contaminated territories

Development of methodology, methods and software for economic activity planning at technogenic contaminated territories

#K-241Radioisotopes in Wild Animals

Studies of Wild Animals Contamination with Fission Products at the Semipalatinsk Test Site

#K-2421Lithium. Tritium.

Hydrogen Isotopes Interaction with Lithium Surfaces of Various States under Reactor Irradiation

#K-414Data Base for Semipalatinsk Test Site

Design, Development and Demonstration of a Comprehensive and Systematic Database of the Semipalatinsk Nuclear Test Site

#K-414-2Data Base for Semipalatinsk Test Site

Design, Development and Demonstration of a Comprehensive and Systematic Database of the Semipalatinsk Nuclear Test Site (DECODA).

#K-513BN-350 Reactor Decommissioning Concept

Preparation of a Decommissioning Plan for International Review to Place the BN-350 Reactor in a SAFESTOR Condition

#K-578Lithium Ceramics for Thermonuclear Reactor

High Li-burnup Irradiation Tests of Ceramic Tritium Breeder

#K-664Welding of Irradiated Reactor Materials

Influence of High-Dose Neutron Irradiation on the Weldability of the BN-350 Fast Nuclear Reactor Materials

#K-670Nonproliferation Monitoring of the Irtysh River Basin

Nonproliferation Monitoring of the Irtysh River Basin. Study of the Irtysh River Basin for the Radioactive and Hazardous Material Contamination

#K-845Direct Acting Safeguard System for Nuclear Reactor

Elaboration a Technology of Direct Acting Safeguard System for Nuclear Reactor, Especially for Projected Kazakstan LWR

#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-935Oncologic Survey of East Kazakhstan

New Technologies of Recording and Epidemiological Analysis of the Indices of Oncologic Sickness and Death Rates among the Population Exposed to Radiation and Non-radiation Environmental Factors in the East-Kazakhstan Region

#K-943Selection of a Radioactive Waste Burial Location

The Study of Nuclear Explosion Deformation Zones in the Azgir Salt Dome to Select Integral Massifs for Locating a Radioactive Waste Burial (RW)

#K-969Scaled-Down Simulation of BN-350 Sodium Coolant Processing Facility

Design and Development of a Scaled-Down Simulation Complex of Automated Control and Dataware System for BN-350 Sodium Coolant Processing Workflow

#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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