Abstract
The superior properties of ferritic/martensitic steels in a radiation environment (low swelling, low activation under irradiation and good corrosion resistance) make them good candidates for structural parts in future reactors and spallation sources. While it cannot substitute for true reactor experiments, irradiation by charged particles from accelerators can reduce the number of reactor experiments and support fundamental research for a better understanding of radiation effects in materials. Based on the nature of low energy accelerator experiments, only a small volume of material can be uniformly irradiated. Micro and nanoscale post irradiation tests thus have to be performed. We show here that nanoindentation and micro-compression testing on T91 and HT-9 stainless steel before and after ion irradiation are useful methods to evaluate the radiation induced hardening.
Original language | English |
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Pages (from-to) | 135-143 |
Number of pages | 9 |
Journal | Journal of Nuclear Materials |
Volume | 375 |
Issue number | 1 |
Early online date | 16 Dec 2007 |
DOIs | |
Publication status | Published - 30 Mar 2008 |
Keywords
- reactor
- steel
- irradiation
- hardness
- nanoindentation