b'APMT, used as reference. Both as-fabricated and pre-oxidized alloys have been tested, in order to evaluate the effectiveness of pre-existingFigure 1.Thermal neutron internal oxide layer in reducingradiography of the ORNL FCCI rodlet.FCCI. The disks of FeCrAl and fuel are retained within an external ring which limits radial swelling of the UO 2fuel as well as favors constant contact between the fuel and cladding disks, forming what is called a H-cup configuration. Each rodlet included a total of 13 H- cups (1 fuel disk and 2 cladding disks per H-cup). The rodlets were inserted for irradiation in the Advanced Test Reactor (ATR) in December 2016. The first rodlet completed irradiation in 2018 and postirradiation examination (PIE) has been conducted on this first rodlet throughout the fiscal year.Accomplishments:The PIE took place in the Hot Fuel Examination Facility (HFEF) at Idaho National Laboratory (INL). The PIE included rodlet visual examination, neutron radiography, gamma scanning, and fission gas release measurements. Thermal neutron radiography is shown in Figure 1. Each H-cup is visible in the radiograph and no major dimensional deformation of the disks occurred. The 2019|AFC ACCOMPLISHMENTS 105'