Microstructural Evolution of NF709 Steel under In-situ Ion Irradiations at Room Temperature to 600 deg. C
NF709 is one of the advanced austenitic stainless steels considered for the advanced reactor systems which are characterized by high temperature, intense radiation and potentially corrosive environments. NF709 is a nitrogen-stabilized and niobium-strengthened alloy, and it provides strength nearly double that for conventional 304 and 316 stainless steels at a temperature range of 600-750 deg. C. In addition, this alloy demonstrates excellent metallurgical stability and high-temperature creep resistance, which is critical for advanced fast-reactor structural materials. Nevertheless, there is very limited irradiation data on NF709 to date, and its radiation-resistance is to be proved. It this paper, we studied the radiation response of NF709 by using the in-situ ion irradiation at the Intermediate Voltage Electron Microscopy (IVEM)- Tandem Facility, located at Argonne National Lab (ANL) and the systematic post-irradiation characterizations using transmission electron microscopy (TEM) were conducted.