|About this Abstract
||2018 TMS Annual Meeting & Exhibition
||Accident Tolerant Fuels for Light Water Reactor
||New Zr-based MAX Phases as Accident Tolerant Fuel Cladding
||David Bowden, Tamas Ungar, Shafqat Shah, Michael Preuss, Philipp Frankel
|On-Site Speaker (Planned)
MAX phases are nanolayered ternary carbides, which exhibit a combination of metallic and ceramic properties. Zr-based materials offer good neutronics and MX-type Zr carbides are shown to offer superior irradiation damage tolerance. New types of Zr-based MAX phases are being studied within the CAFFE (carbides for future fission environments) consortium, which is assessing the optimal stoichiometry and suitability of these new materials for generation III+ nuclear environments. Proton irradiated Zr-based MAX phase alloys have been produced and subsequently analysed using several x-ray diffraction (XRD) techniques. XRD allows us to measure irradiation-induced microstructural changes, such as the alteration of lattice parameters and atomic positions within these materials. Alongside this, we can utilise line profile analysis techniques to calculate any changes in dislocation density arising from irradiation. These results are compared to modelled data which predicts lattice changes due to differing types of defect accumulation, such as antisite defects and Frenkel pairs.
||Planned: Supplemental Proceedings volume