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Radiation Resistance of Ultrafine Grained Stainless Steels


Radiation Resistance of Ultrafine Grained Stainless Steels

Tech Area / Field

  • FIR-MAT/Materials/Fission Reactors
  • MAT-ALL/High Performance Metals and Alloys/Materials

3 Approved without Funding

Registration date

Leading Institute
National Nuclear Center of the Republic of Kazakstan / Institute of Nuclear Physics, Kazakhstan, Almaty


  • Japan Atomic Energy Agency, Japan, Ibaraki

Project summary

The proposed research focuses on austenitic stainless steels (301/304/316SS), operated in the core of nuclear reactors under an intensive impact of neutron flux, temperature gradients and stresses. The project examines radiation damage effects on ultrafine grain structures (up to 5ìm) of reactor steels and carries out comparison analysis with similar effects to conventional microstructure. The primary aim of the research is to clarify the mechanisms describing the radiation-induced hardening and embrittlement (i.e., reduction in the ductility characteristics) by carrying out neutron irradiation in the WWR-K reactor (Almaty) of traditional and fine-grained austenitic steels. The subsequent investigations will be followed by performing comparative complex materials science studies and data analysis (mechanical testing at different temperatures, corrosion testing, magnetometry, microhardness and electron microscopy).


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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