Reduced activation ferritic martensitic (RAFM) and oxide dispersion strengthened (ODS)
steels are the most promising candidates for fusion first-wall/blanket (FW/B) structures. The …

Current phenomenological knowledge and understanding of mechanisms are reviewed for
radiation embrittlement of reactor pressure vessel low alloy steels and irradiation assisted …

Understanding the behavior of reactor pressure vessel (RPV) steels under irradiation is a
mandatory task that has to be elucidated in order to be able to operate safely a nuclear …

This paper melds an overview of the history of Reactor Pressure Vessel (RPV) embrittlement
research, focusing on predicting ductile-to-brittle transition temperature shifts (ΔT), along …

A high-purity binary alloy Fe18Cr was subjected to heavy-ion irradiation in order to provide
improved understanding of the irradiation effect on radiation hardening associated with …

The amorphous AlCrFeMoTi high-entropy alloy (HEA) coating with near-equal molar ratio
was successfully deposited on F/M substrate by magnetron co-sputtering technique and …

The formation of nano-sized, coherent, solute-rich clusters (NSRC) is known to be an
important factor causing the degradation of the macroscopic properties of steels under …

Nanometric voids are one of the fundamental defects generated by neutron irradiation in
fusion environment, which impede dislocation motion and cause hardening of plasma facing …

Abstract Development of irradiation hardening models attracts extensive attention in
designing nuclear materials. Dislocation dynamics (DD) method is a powerful tool in this …

Ion irradiation is usually used to simulate neutron irradiation to accelerate the evaluation of
the irradiation behavior of reactor materials. However, the validity of using a high damage …