| About this Abstract |
| Meeting |
Materials in Nuclear Energy Systems (MiNES) 2021
|
| Symposium
|
Materials in Nuclear Energy Systems (MiNES) 2021
|
| Presentation Title |
Dose and Temperature Effect on Dispersoids in Neutron Irradiated Oxide Dispersion Strengthened (ODS) Alloys |
| Author(s) |
Samara Michelle Levine, Arunodaya Bhattacharya, Jonathan Poplawsky, Andrew Lupini, David Hoelzer, Yutai Katoh, Steven Zinkle |
| On-Site Speaker (Planned) |
Samara Michelle Levine |
| Abstract Scope |
Although ODS alloys are among the leading candidates for fusion first-wall/blanket (FW/B) structures, the effect of fusion-relevant irradiation on these advanced materials is still not well-understood. Here, three ODS steel variants (12%Cr 12YWT, 14%Cr MA957, and 20%Cr-5.5%Al PM2000) were neutron irradiated in the high-flux isotope reactor (HFIR) at 300-500°C for ~3.5-80 dpa. Previously we revealed at low temperatures and high doses, transformation of the nano-dispersoids included cavitation, amorphization, and formation of internal “cherry-pit” structures. Here we expand upon the effects of neutron dose and temperature on nano-dispersoid stability using analytical scanning transmission electron microscopy (STEM) and atom probe tomography (APT). Possible mechanisms are presented to explain structure-chemistry evolution of the nano-dispersoids. Research sponsored by the U.S. Department of Energy, Office of Fusion Energy Sciences, under contract DE-AC05-00OR22725 with UT-Battelle, LLC. APT/STEM was conducted at CNMS, which is a DOE Office of Science User Facility. Work supported under UTK’s GATE Fellowship. |
| Proceedings Inclusion? |
Undecided |