Abstract and subjects
The reduced activation ferritic/martensitic alloy F82H (Fe–8Cr–2W–0.2V–0.04Ta–0.1C) is being considered as a structural material for several different fusion related nuclear applications. The oxide dispersion strengthened (ODS) alloys Fe–8Cr–2W ODS and Fe–8Cr ODS were developed for better high-temperature strength and radiation tolerance. These materials have been exposed to a neutron and proton environment in the Spallation Target Irradiation Program (STIP) (<13dpa) with an average He/dpa ratio of 60appm He/dpa at irradiation temperatures 159–347°C. After irradiation, the samples were tensile tested at different temperatures. The post tensile testing fractured parts were collected and nanoindentation, microcompression testing and local electrode atom probe was conducted. The information gained by local electron atom probe in combination with the micro, nano and macroscopic mechanical tests allows one to establish a fundamental understanding of the relationship between the data measured at different scales on irradiated materials.