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#0465Radioactive Safety under Reactors Decommissioning

The Safety Insurance at Decommissioning of Reactor Installations of Civil and Military Application.

#0561Tomsk-7 Graphite Contamination

Determination of Radioactive Contamination of Weapons-grade Pu Production Reactors Graphite of Siberian Groups of Chemical Enterprises, SGCE, (Tomsk-7).

#0779Dismantling of BR-10 Fast Reactor

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

#0841Radioactive Inventory for Decommissioning Reactors

Evaluation of Radioactive Inventory for Fission Reactor Decommissioning

#1192New Concept of Reactor Decommissioning

Concept Development of Innovation Technology for Decommissioning of Nuclear Power Plants. Calculation, Experimental, Technical and Economic Studies in Justification of the Concept

#1243Radioactive Graphite Handling

Technical and Economic Grounds for the Development and Introduction of Radiation Safe Technology for Handling and Treatment of Spent Radioactive Graphite from RBMK-Type Reactors

#1731Water-Jet Cutting for Submarine Dismantlement

Technology of Nuclear Submarine Dismantlement Using Abrasive Water-Jet Cutting Method

#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

#2911Power Fast Reactor Radioactive Sodium

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

#A-1295Armenian Nuclear Power Plant Decommissioning

Radiological Characterization and Database Creation in Support of ANPP Decommissioning Planning

#G-409Modelling of the Power Nuclear Facility

Calculation of Parameters of Low Power Nuclear Facility Provided by Conversion Program of the Research Nuclear Reactor of the E. Andronikashvili Institute of Physics of the Georgian Academy of Sciences on the Basis of Computer Program Developed in USA

#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-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-512Cesium Trap for BN-350 Reactor

Develop, Install, and Operate a Cesium Trap, Based on the U.S. Technologies, to Reduce Cesium Levels in the BN-350 Primary Sodium and Enhance Plant Fire Protection Capabilities to Support Cesium Trap Operation

#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-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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