| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components IV
|
| Presentation Title |
Mechanical Properties of Tempered Martensitic Steels after High Dose Fast Reactor Irradiations |
| Author(s) |
Stuart Andrew Maloy, Nathan Bailey, Ramprashad Prabhakaran, Eda Aydogan, Md Ershadul Alam, Mychailo Toloczko |
| On-Site Speaker (Planned) |
Stuart Andrew Maloy |
| Abstract Scope |
The Advanced Fuels Campaign is developing and qualifying fuels for advanced reactors. To achieve this goal, new fuels and cladding materials are being tested to high burnup levels (e.g. >20%) which require cladding to withstand very high doses (greater than 200 dpa) while in contact with the coolant and the fuel. Tempered Martensitic Alloys are the leading candidates for these extreme service conditions. High dose irradiations were previously performed on ferritic/martensitic steels in the Fast Flux Test Facility and are available for testing. Select high dose specimens (up to 100 dpa) were tested in tension and properties are being correlated with microstructure and compared previous research. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Characterization, Mechanical Properties, Nuclear Materials |