|About this Abstract
||2017 TMS Annual Meeting & Exhibition
||Energy Materials 2017: Materials for Nuclear Energy
||Systematic Studies on Dispersoid Stability and Swelling Resistance in ODS Alloys under Ion Irradiation Conditions
||Hyosim Kim, Jonathan Gigax, Tianyi Chen, Frank Garner , Lin Shao
|On-Site Speaker (Planned)
Oxide-dispersion-strengthened (ODS) alloys are candidates for structural components of advanced reactors. Here we first compare the swelling resistance during high dose ion irradiation of a wide variety of commercially available ODS alloys, from easily-swelling MA 956 with unstable dispersoids to very swelling-resistant 12 Cr ODS variants with relatively stable dispersoids. The second material focus involves three new developmental ODS variants, seeking further optimization of swelling resistance by varying thermal-mechanical treatment and alloying elements such as Al, Ni, W, and O, to produce oxide dispersoids of different densities, sizes and interface coherency. Using 3.5 MeV Fe ion irradiation, these alloy variants were irradiated at various irradiation temperatures, displacement-per-atom (dpa) values, and dpa rates. This study provides comprehensive experimental data on dispersoid stability to compare with our previously published theoretical model in which temperature, dpa, dpa rate and interface coherency are key parameters to predict dispersoid shrinkage or growth under irradiation.
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