The oxide dispersion strengthened (ODS) ferritic steels containing Zr are synthesized with
and without Al addition and found to possess homogeneous distribution of nanoprecipitates …

A large number of dislocation networks were introduced in to 316L stainless steel by cold
rolling. Subsequently, low energy (40 eV) helium ions were implanted by exposing the steel …

In the fusion reactors, plasma facing materials (PFMs) will be bombarded by large amounts
of energetic particles, including helium (He) atoms. These metal-insoluble He atoms are …

The formation of hydrogen and helium associated defect complexes and their influence on
the nucleation and growth of helium bubbles in Indian Reduced Activation …

Structural materials used in nuclear reactors face many challenges due to elevated
temperature operation, high neutron flux induced transmutations and radiation damage. In …

In the present paper, we employ the depth sensitive slow positron Doppler broadening
technique to characterise the positron diffusion in various near-surface layers of He+ …

Tungsten has been considered as a potential candidate material for the application of
plasma-facing components in magnetic confinement fusion reactors. Fusion neutrons …

This study explores the effects of Fe ion irradiation and helium implantation on the
mechanical and microstructural behaviors of K-RAFM steels. Through micropillar …

High-temperature irradiation damage studies of Indian Reduced Activation
Ferritic/Martensitic (INRAFM) steel have been carried out at doses relevant to fusion reactor …

Indian reduced activation ferritic-martensitic steel was irradiated with 1.1 MeV Fe ions to
various doses from 1 to100 dpa at room temperature. The depth profiling of irradiation …