Overview of irradiation stability of oxide particles in ODS steels for nuclear systems

Oxide dispersion strengthened (ODS) steels are candidate materials for fuel claddings of Generation IV nuclear reactors as well as for the structural components of the fusion reactor due to its superior high temperature creep properties and good irradiation resistance. ODS steels are expected to be used under a long time high dose neutron radiation up to 200 dpa at an elevated temperature up to 973K, so the effects of a neutron radiation on mechanical properties and microstructural stabilities of ODS steels are primary concerns to be investigated. Since the presence of stable and fine oxide particles are critical to the good high temperature strength and creep properties of ODS steels, it shall be essential to understand and maintain the stability of the oxide particles under irradiation. This paper gives an overview of the recent progress in this field