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 124Nuclear Science User Facilities 66 Synchrotron X-Ray Characterizations of Advanced Accident-tolerant Cladding Kun Mo – Argonne National Laboratory – mokun2004@gmail.com This research aims to char- acterize the microstructural development of intermetallic coated zircaloy, an advanced cladding material, after heavy ion irradiation. The intermetallic coatings on the zircaloy were developed using atomic layer deposition (ALD) technique. With the protection of the coating, the oxidation resistance of the zircaloy has been significantly improved. However, the performance of the coating in a highly radioactive environment is not yet understood. In this study, the synchrotron X-ray available at the Materials Research Collaboratory AccessTeam (MRCAT) beamline at the Advanced Photon Source (APS) was utilized to study the materials’ performance after high-energy heavy ion irradiation.An X‑ray absorption fine structure (XAFS) experiment was conducted to study the ion radiation damage on the zircaloy sample with advanced coatings. Project Description Advanced intermetallic coatings have great potential for improving resistance to oxidation and radiation damage in nuclear materials.The Fukushima Daiichi nuclear accident has clearly demonstrated to the world that improvement of the safety performance of operating light water nuclear reactors (LWRs) is an imminent need.The reactors at the Fukushima Daiichi Nuclear Power Plant experienced a loss of coolant accident (LOCA) during which the zirconium alloy (zircaloy) cladding (sealed tubes that protect the UO2 fuel material from contact with the environment) experienced severe oxidation. Large amounts of hydrogen were generated as steam reacted with zirconium at high temperature, eventually leading to hydrogen explosions. In response to the accident, the U.S. Department of Energy (DOE) Office of Nuclear Energy (NE) has placed strong strategic importance on developing LWR fuels with enhanced accident Advanced intermetallic coatings on zircaloy cladding have great potential for improving resistance to oxidation and radiation damage.