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#K-664Welding of Irradiated Reactor Materials

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

#K-1250Data on Steel Irradiated in Fast Reactor

Application of BN-350 Data on Ferritic-Martensitic Steel to International Efforts on Advanced Reactor Concepts (Fusion, Accelerator-Driven, Generation-4)

#K-812.2Fuel Assembly Materials under Dry Storage

Behavior of Nuclear Reactor Fuel Assembly Materials during Their Long-Term Dry Storage

#K-437.2Fast Reactor Materials Properties

Application of Structural Materials Data from the BN-350 Fast Reactor to Life Extension of Light Water Reactors


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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