Quantitative APT analysis of solid transmutants in ferritic-martensitic steels after irradiation in SINQ targets: Experimental validation of neutronic calculations

• Solid transmutants in irradiated F82H, Eurofer 97 and ODS were quantitatively analyzed with APT. The results of the APT analysis provide experimental validation neutronic calculations applied to STIP irradiation experiments. properties materials fission fusion reactors targets spallation neutron sources can be greatly degraded by radiation-induced transmutants. A precise prediction production is highly important for safety assessment these facilities. normally made using calculations. Experimental calculation essentially necessary, but usually very challenging. In present work, a quantitative ferritic-martensitic (FM) steels 97, after at 9.6 19.6–21 dpa SINQ was performed Atom Probe Tomography (APT). indicate that solid Ti, Sc, Ca, K, Cl, S precisely measured gas element Ar could also detected. difference between concentrations calculated MCNPX code less than 30% most detectable nuclides This work demonstrates experiments are reliable.