Page 1 Page 2 Page 3 Page 4 Page 5 Page 6 Page 7 Page 8 Page 9 Page 10 Page 11 Page 12 Page 13 Page 14 Page 15 Page 16 Page 17 Page 18 Page 19 Page 20 Page 21 Page 22 Page 23 Page 24 Page 25 Page 26 Page 27 Page 28 Page 29 Page 30 Page 31 Page 32 Page 33 Page 34 Page 35 Page 36 Page 37 Page 38 Page 39 Page 40 Page 41 Page 42 Page 43 Page 44 Page 45 Page 46 Page 47 Page 48 Page 49 Page 50 Page 51 Page 52 Page 53 Page 54 Page 55 Page 56 Page 57 Page 58 Page 59 Page 60 Page 61 Page 62 Page 63 Page 64 Page 65 Page 66 Page 67 Page 68 Page 69 Page 70 Page 71 Page 72 Page 73 Page 74 Page 75 Page 76 Page 77 Page 78 Page 79 Page 80 Page 81 Page 82 Page 83 Page 84 Page 85 Page 86 Page 87 Page 88 Page 89 Page 90 Page 91 Page 92 Page 93 Page 94 Page 95 Page 96 Page 97 Page 98 Page 99 Page 100 Page 101 Page 102 Page 103 Page 104 Page 105 Page 106 Page 107 Page 108 Page 109 Page 110 Page 111 Page 112 Page 113 Page 114 Page 115 Page 116 Page 117 Page 118 Page 119 Page 120 Page 121 Page 122 Page 123 Page 1242015 | ANNUAL REPORT 93 Oxide nanocluster evolution in Fe-9%Cr ODS differs between heavy ion, proton, and neutron irradiation. the alloying additions of the AA6061. This study seeks to determine the effect of the minor element additions in the AA6061 and to identify any phases that may have developed as a result of these additions. Project Description Specimens of a model Fe-9%Cr oxide dispersion strengthened (ODS) alloy have been irradiated with neutrons in the AdvancedTest Reactor (dose rate ~10−7  dpa/sec), with 2.0 MeV protons (~10−5 dpa/sec) and with 5.0 MeV self-ions (~10−4  dpa/ sec).All irradiations were carried out to 3 dpa at a temperature of 500°C. The microstructure of each specimen was characterized using transmission electron microscopy and atom probe tomography (with cluster analysis) and compared to the microstructure of the original as-received sample. Nanoindentation was used to measure any relative change in hardness as a result of each irradiation. Because this project aims to (1) understand the response of advanced reactor candidate structural mate- rials to irradiation, and (2) assess the ability of proton and heavy ion irradiations to emulate in‑reactor neutron irradiation damage, this project has direct relevance to the Department of Energy Office of Nuclear Energy’s (DOE-NE’s) Advanced ReactorTechnologies program.The primary DOE‑NE mission is to advance nuclear power as a resource capable of meeting the nation’s energy, environmental, and national security needs. Generation IV advanced reactor designs, such as high‑temperature reactors and fast neutron spectrum reactors, fulfill this mission by coupling high-efficiency power generation with the environ- mental and national security benefits of consuming long-lived radioac- tive isotopes found in used nuclear fuel. However, with the promise of Generation IV designs comes the challenge of finding suitable structural materials that will withstand the harsh in-reactor operating condi- tions. Ensuring the integrity of these materials under high temperatures, corrosive environments, cyclic loading, and high-irradiation damage, is paramount to the safety, perfor- mance, and long-term success of the Generation IV nuclear fleet. Accomplishments In this project, we compared the microstructure evolution of the iden- tical heat of a model Fe‑9%Cr ODS under self‑ion, proton, and neutron irradiation, all carried out at 500°C to 3 dpa. NSUF enabled the team to access neutron‑irradiated specimens