About this Abstract |
Meeting |
2022 TMS Annual Meeting & Exhibition
|
Symposium
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Mechanical Behavior and Degradation of Advanced Nuclear Fuel and Structural Materials
|
Presentation Title |
Study of the Irradiation Induced Microstructure and Mechanical Properties in Low Alloyed Ferritic Steels |
Author(s) |
Maria Vrellou, Bertrand Radiguet, Akiyoshi Nomoto, Philippe Pareige |
On-Site Speaker (Planned) |
Maria Vrellou |
Abstract Scope |
Irradiation modifies the microstructure of the Nuclear Power Plant’s structural materials, causing embrittlement and thus possibly limiting their integrity for long term operation. Some details of underlying mechanisms driving this process remain still unclear since the induced microstructure depends on many parameters concerning both irradiation conditions and material history and environment.
This study aims to evaluate the impact of Ni, Mn, their synergistic effect and the effect of Cu, on the neutron irradiation induced microstructure of 4 selected model alloys (Fe-1.1Mn-0.7Ni, Fe-1Mn, Fe-1Ni and Fe-0.1Cu), correlating it with the change in their mechanical properties. For this, the unirradiated and irradiated alloys’ microstructure is determined by APT. Irradiation induced hardening calculated from the stress-strain curves is obtained by in-situ micro-compression of FIB-fabricated micropillars. To corelate the irradiation induced microstructure with measured hardening, APT tips and TEM lamellas are lifted out from the compressed pillars. The results will be presented and discussed. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, |