2017 | AFC ACCOMPLISHMENTS 177 to ongoingirradiations in HFIR. (Saleh, Romero, LANL) Microstructural analysis (Figure 3) of HFIR irradiated FeCrAl Alloys (Field, ORNL) Figure 2. Room and elevated temperature (250C) tensile tests of control GenII FeCrAl alloys. Figure 3. Synthetic Microstructures of alpha’ ingrowth in GenI FeCrAl alloys irradiated at 320C and 7dpa, generated from SANS data. Project Description: Due to the Fukishima accident of 2011 interest in the accident tolerant fuels and cladding materials have increased. Research into claddings that are resistant to the high temperature steam oxidation conditions seen in loss of coolant accidents (LOCA) have led studies of iron-Chromium-Alumium (FeCrAl) alloys, which form a protec- tive aluminum oxide layer under these conditions. Irradiations of these alloys are underway in the HFIR at Oak Ridge National Laboratory (ORNL).Alloys of various Cr content are being studied to understand the effects of irradiation produced Cr rich alpha’ phase on the mechanical properties of these alloys. This report presents mechanical testing on four first generation (GenI) FeCrAl alloys of varying Cr (10-18 wt%) andAl (3-5 wt%) content that were irradiated to 320C and 7 dpa in the HFIR reactor, as well control samples of two second generation (GenII) FeCrAl alloys of varying Cr content (10 and 13 wt%) that will be used for comparison to samples that are currently being irradi- ated in the HFIR reactor. Accomplishments: Ship irradiated samples from ORNL hot cells to complete these tensile experiments and provide samples for futureirradiated material mechanical testing (shear punch and high temperature tensile tests) (Quintana, Saleh, LANL, Field ORNL) Uniaxial tension of HFIR irradiated FeCrAl alloys at additional tempera- tures and conditions to compliment and expand exisiting work. (Saleh, Romero, LANL) Uniaxial tension of GenII FeCrAl control specimens to create a data- base of unirradiated data to compare