Abstract
Radiation-induced segregation in ferritic-martensitic alloy T 91 was studied to understand the behavior of solutes as a function of dose and temperature. Irradiations were conducted using 2 MeV protons to doses of 1, 3, 7 and 10 dpa at 400 °C. Radiation-induced segregation at prior austenite grain boundaries was measured, and various features of the irradiated microstructure were characterized, including grain boundary carbide coverage, the dislocation microstructure, radiation-induced precipitation and irradiation hardening. Results showed that Cr, Ni and Si segregate to prior austenite grain boundaries at low dose, but segregation ceases and redistribution occurs above 3 dpa. Grain boundary carbide coverage mirrors radiation-induced segregation. Irradiation induces formation of Ni-Si-Mn and Cu-rich precipitates that account for the majority of irradiation hardening. Radiation-induced segregation behavior is likely linked to the evolution of the precipitate and dislocation microstructures.
| Original language | English |
|---|---|
| Pages (from-to) | 140-144 |
| Number of pages | 5 |
| Journal | Journal of Nuclear Materials |
| Volume | 417 |
| Issue number | 1-3 |
| DOIs | |
| State | Published - Oct 1 2011 |
Funding
The authors gratefully acknowledge Ovidiu Toader and Fabian Naab for their assistance in conducting proton irradiation. The authors also acknowledge the facilities provided by the Michigan Ion Beam Laboratory, the Electron Microbeam Analysis Laboratory at University of Michigan and the Central Analytical Facility at the University of Alabama. A portion of this research was conducted at the SHaRE User Facility, which is sponsored by the Division of Scientific User Facilities, Office of Basic Energy Sciences, US Department of Energy. Support for this research was provided by the Department of Energy under Awards # DE-FG07-07ID14894 and # DE-FC07-07ID14828.
| Funders | Funder number |
|---|---|
| U.S. Department of Energy | DE-FC07-07ID14828, DE-FG07-07ID14894 |
| Basic Energy Sciences |