Divertor and Transport System for Fusion Devices
Creation of a Comprehensive Database of the Former Semipalatinsk Test Site
Semipalatinsk Test Site Environment Assessment Using Bioindication Methods
Development and Manufacturing of Demonstration Models of KTM Tokamak Divertor In-Vessel Plasma Facing Elements on the Base of Liquid Lithium
Reactor Studies of Lithium CPS
Estimation of Radiological Safety on Sites of Series of Technological Peaceful Nuclear Explosions in Kazakhstan
Development of methodology, methods and software for economic activity planning at technogenic contaminated territories
Studies of Wild Animals Contamination with Fission Products at the Semipalatinsk Test Site
Hydrogen Isotopes Interaction with Lithium Surfaces of Various States under Reactor Irradiation
Design, Development and Demonstration of a Comprehensive and Systematic Database of the Semipalatinsk Nuclear Test Site
Design, Development and Demonstration of a Comprehensive and Systematic Database of the Semipalatinsk Nuclear Test Site (DECODA).
Preparation of a Decommissioning Plan for International Review to Place the BN-350 Reactor in a SAFESTOR Condition
High Li-burnup Irradiation Tests of Ceramic Tritium Breeder
Influence of High-Dose Neutron Irradiation on the Weldability of the BN-350 Fast Nuclear Reactor Materials
Nonproliferation Monitoring of the Irtysh River Basin. Study of the Irtysh River Basin for the Radioactive and Hazardous Material Contamination
Elaboration a Technology of Direct Acting Safeguard System for Nuclear Reactor, Especially for Projected Kazakstan LWR
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
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
The Study of Nuclear Explosion Deformation Zones in the Azgir Salt Dome to Select Integral Massifs for Locating a Radioactive Waste Burial (RW)
Design and Development of a Scaled-Down Simulation Complex of Automated Control and Dataware System for BN-350 Sodium Coolant Processing Workflow
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.