Two ferritic Oxide Dispersion Strengthened (ODS) steels Fe-12Cr-YWT and Fe-14Cr-YWT were irradiated in the High Flux Reactor (HFR) up to 3 dpa at a nominal temperature of 600°C. Tensile tests at room and elevated temperatures as well as microstructural investigations using transmission electron microscopy (TEM) and atom probe tomography (APT) were…
Most research reactors (RRs) in Europe are over 60 years old, and there are only limited efforts underway (e.g.,
PALLAS and JHR projects) to partially replace this aging infrastructure. Continued safe operation (CSO) of these
reactors is crucial to sustaining the EU’s leadership in nuclear materials development and qualification for advanced
r…
