2017 | AFC ACCOMPLISHMENTS 179 Experiment ID and Position Fuel Composition ID Neutron Flux (n/cm2 /sec) HGR (W/g) LHGR (W/cm) Fission Density (fissions/cc) HM Burnup (atom %) U-235 Burnup (atom %) EOC 60.1 Days 60.1 Days AFC-3F A-11 @23.0 MW 3F-1 4.99E+14 162.15 365.53 7.896E+20 2.12% 4.09% 3F-2 7.95E+14 155.22 343.68 7.488E+20 2.06% 8.34% 3F-3 8.85E+14 172.78 378.08 7.821E+20 2.19% 9.60% 3F-4 8.57E+14 160.16 361.15 7.577E+20 2.10% 9.31% 3F-5 6.46E+14 186.97 416.72 8.577E+20 2.36% 5.41% MAX 8.85E+14 186.97 416.72 8.577E+20 2.36% 9.60% Experiment ID and Position Fuel Composition ID Neutron Flux (n/cm2 /sec) HGR (W/g) LHGR (W/cm) Fission Density (fissions/cc) HM Burnup (atom %) U-235 Burnup (atom %) EOC 60.1 Days 60.1 Days AFC-4C A-10 @25.9 MW 4C-1 5.31E+14 197.62 332.31 1.333E+21 3.82% 7.36% 4C-2 8.98E+14 152.33 354.28 1.159E+21 2.92% 13.47% 4C-3 1.04E+15 159.36 352.01 1.110E+21 3.11% 16.39% 4C-4 9.68E+14 161.17 331.00 1.051E+21 3.23% 15.33% 4C-5 6.95E+14 157.60 355.27 1.129E+21 3.10% 9.79% MAX 1.04E+15 197.62 355.27 1.333E+21 3.82% 16.39% Table 1. AFC - 4F Irradiation Phase Experimental Data. Table 2. AFC - 4C Irradiation Phase Experimental Data.