In situ neutron diffraction and Elastic–Plastic Self-Consistent polycrystal modeling of HT-9

Abstract Qualifying materials for use in reactors with fluences greater than 200 dpa (displacements per atom) requires development of advanced alloys and irradiations in fast reactors to test these alloys. Research into the mechanical behavior of these materials under reactor conditions is ongoing. In order to probe changes in deformation mechanisms due to radiation in these materials, samples of HT-9 were tested in tension in situ on the SMARTS instrument at Los Alamos Neutron Science Center. Experimental results, confirmed with modeling, show significant load sharing between the carbides and parent phase of the steel beyond yield, displaying the critical role of carbides during deformation, along with basic texture development.