Abstract
Austenitic stainless steels are widely used in current commercial BWR and PWR systems as in-core and surrounding structural materials. These versatile steels have also been the main materials considered and applied for many advanced reactor technologies, including fast-breeder reactors and magnetic fusion reactors. For advanced reactors for higher temperatures or high lifetime damage levels, modified versions of the standard commercial stainless steel grades have been developed to provide improved performance properties and radiation resistance in specific reactor environments. An overview of the unirradiated properties and a summary of some important radiation-induced changes in properties are presented. The development of several alloys for more radiation resistance or better performance in specific reactor environments is highlighted.
| Original language | English |
|---|---|
| Title of host publication | Comprehensive Nuclear Materials |
| Subtitle of host publication | Volume 1-5 |
| Publisher | Elsevier |
| Pages | 267-283 |
| Number of pages | 17 |
| Volume | 1-5 |
| ISBN (Electronic) | 9780080560335 |
| ISBN (Print) | 9780080560274 |
| DOIs | |
| State | Published - Jan 1 2012 |
Funding
Research sponsored by the U.S. Department of Energy (DOE), Office of Nuclear Energy, for the FCRD & Gen-IV Research Program, under contract DE-AC05-00OR22725 with UT-Battelle, LLC.
| Funders | Funder number |
|---|---|
| U.S. Department of Energy | |
| Office of Nuclear Energy | |
| Canadian Foundation for Dietetic Research | DE-AC05-00OR22725 |
Keywords
- Advanced reactor technologies
- Aging
- Austenitic stainless steels
- Creep rupture
- Fabrication
- High temperature
- Mechanical properties
- Microstructure
- Physical properties
- Precipitation
- Processing behavior
- Radiation resistance
