Abstract
Ferritic steels are interesting for fast reactor core application because of the absence of swelling. As canning material, because of the higher temperature involved, new ferritic steels with oxide dispersion strengthening were developed. Fabrication methods are given and their mechanical irradiation and sodium compatibility properties are reviewed.
Original language | English |
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Pages (from-to) | 215-219 |
Number of pages | 5 |
Journal | Nuclear Technology |
Volume | 70 |
Issue number | 2 |
DOIs | |
State | Published - 1985 |
ASJC Scopus subject areas
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering
- Condensed Matter Physics