|About this Abstract
||2020 TMS Annual Meeting & Exhibition
||Accelerated Materials Evaluation for Nuclear Applications Utilizing Irradiation and Integrated Modeling
||In-situ Heavy Ion Irradiation of FCC and BCC High-entropy Alloys at Cryogenic and High Temperatures
||Calvin A. Parkin, Michael Moorehead, Mohamed Elbakhshwan, Jing Hu, Wei-Ying Chen, Kumar Sridharan, Adrien Couet
|On-Site Speaker (Planned)
||Calvin A. Parkin
In-core structural materials for SFR cladding are expected to demonstrate radiation tolerance up to several hundreds of displacements per atom (dpa) over the operating lifetime. High-entropy alloys (HEA) consisting of four or more principle alloying elements in single-phase solid solution are theorized to resist radiation due to unique energy and mass transport properties. The dependence of microstructural evolution on irradiation temperature and compositional complexity is expected to reveal these radiation tolerance mechanisms. In situ heavy-ion irradiation experiments up to 2 dpa were performed at the IVEM facility at ANL. HEA from the CrFeMnNi (FCC) and NbTaTiV (BCC) families, whose phase evolutions were modeled by CALPHAD, were compared to less compositionally complex reference materials at irradiation temperatures of 50K, 300K, and 773K. Small defect clusters and prismatic loops were observed and quantified in all alloys as function of dose and temperature. The effect of compositional complexity on irradiation response is discussed.