Characterisation of ODS Fe-14Cr-2W-0.3Ti before and after high temperature triple and low temperature single ion irradiations
Oxide dispersion strengthened reduced activation ferritic steels are being considered as structural materials for future fusion reactors and Gen IV fission reactors. In this work, the stability of the nanometric oxides after being irradiated at different conditions and temperatures has been investig...
| Үндсэн зохиолчид: | , , , , , , |
|---|---|
| Формат: | Journal article |
| Хэл сонгох: | English |
| Хэвлэсэн: |
Elsevier
2017
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