Abstract
Ten alloys including austenitic stainless steels 316L and 310; Ni-base alloys X750, 718, 725, 690, 625, and C22; and advanced ferritic alloys T92 (optimized) and 14YWT were irradiated in dual ion mode at 400 °C with ∼5 MeV self-ions to a damage level of 150 dpa and with degraded 2 MeV helium to a concentration of ∼13 appm He/dpa. Irradiation-induced dislocation loops and nanoscale cavities were observed across the alloys, but with only modest swelling. Pre-existing γ ′ and γ ″ precipitates were dissolved or chemically disordered by irradiation, while irradiation-induced phases (e.g., Ni 2 Cr, G-phase) did not form. In terms of microstructural change, the ferritic alloys, as a class, showed the best radiation resistance while the austenitic stainless steels showed the worst. Radiation resistance among the Ni-base alloys varied significantly, with precipitation-hardened alloys performing worse and dislocation loop content increasing with iron content. These findings were in broad agreement, qualitatively and quantitatively, with past dual beam and in-reactor irradiations of structural materials, demonstrating the utility of dual ion irradiations to capture key evolution quickly and accurately.
| Original language | English |
|---|---|
| Pages (from-to) | 125-134 |
| Number of pages | 10 |
| Journal | Journal of Nuclear Materials |
| Volume | 516 |
| DOIs | |
| State | Published - Apr 1 2019 |
| Externally published | Yes |
Funding
The authors wish to acknowledge the financial support of the Electric Power Research Institute (contract 10002164 ) and U.S. Department of Energy (contract 4000136101 ). The authors also thank O. Toader, T. Kubley, and E. Uberseder (formerly) of MIBL as well as S. Taller and D. Woodley of the University of Michigan for their assistance with the dual ion irradiations. Similar thanks are given to the Michigan Center for Materials Characterization for use of their instruments and staff assistance, particularly of Dr. K. Sun. The authors recognize Dr. L. Tan of ORNL for providing the optimized heat of T92 used here, while Dr. S. Maloy of LANL, Dr. D. Hoelzer of ORNL, and Prof. R. Odette of the University of California, Santa Barbara are acknowledged for providing the alloy 14YWT.
Keywords
- Radiation damage
- Structural materials
- Swelling