Phase stability of ods particles in ferritic martensitic steels

The development of innovative nuclear energy technologies requires extensive research to create materials that can resist tough radiation conditions (high temperature, intense flow of fast neutrons, corrosion) and provide the desired operating life (60 years). Development and creation of oxide dispersion-strengthened (ODS) ferritic-martensitic steels, obtained by mechanical alloying (MA) powders Fe, Cr, W, Ti and nano-sized grains (20 nm) of refractory oxides (Al2O3, TiO2, Y2O3 etc.), allows to hope to increase the radiation resource of structural elements fabricated up to 200 dpa The study of the microstructure of MA/ODS/FM steels fuel rod cladding fast reactor irradiated by a dose of approximately to 160 dpa and found the decrease in density, size, volume fraction and the elemental composition of the oxide dispersion, providing the duration of the incubation period of vacancy swelling, dimensional stability and structural elements increase their operational resource. This paper deals with the mechanisms of radiation dissolution of oxide particles and their elemental composition change during irradiation. The processes of evolution of the microstructure under high radiation irradiation are considered from the perspective of dynamic instability, self-organization and restructuring of the nonlinear radioactive processes.