| About this Abstract |
| Meeting |
Materials in Nuclear Energy Systems (MiNES) 2021
|
| Symposium
|
Materials in Nuclear Energy Systems (MiNES) 2021
|
| Presentation Title |
Physical Understanding of Radiation Hardening of Neutron Irradiated FeCr Alloys |
| Author(s) |
Cristelle Pareige, A. Etienne, P-M. Gueye, M. Hernandez-Mayoral, A. Ulbricht, F. Bergner, C. Heintze, L. Malerba, N. Castin, G. Bonni, M. J. Konstantinovic |
| On-Site Speaker (Planned) |
Cristelle Pareige |
| Abstract Scope |
High-chromium ferritic-martensitic steels are promising candidates for structural components in Gen-IV and fusion reactors because of their excellent swelling resistance and good thermal properties. At low temperature, the operating window is limited by irradiation hardening and the correlated embrittlement. These are influenced by Cr content but also by impurity content (Ni, Si, P and C) and initial microstructure (ferritic vs martensitic). We investigated these factors in neutron irradiated Fe9Cr alloys and steels with advanced experimental techniques, including PAS, SANS, TEM, APT and mechanical testing. These experimental results are simulated and interpreted from the point of view of the physical mechanisms that drive the microstructure evolution using a physical model that also provides a quantitative prediction of the ensuing radiation hardening and embrittlement, bridging the formation of nano-sized solute clusters with hardening or embrittlement. This work is part of the H2020/M4F project and of the EERA/JPNM. |
| Proceedings Inclusion? |
Undecided |