About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Developments in Advanced Nuclear Structural Materials
|
| Presentation Title |
Development and Testing of Advanced Ferritic Steels for Fast Reactor Applications |
| Author(s) |
Stuart Andrew Maloy, Eda Aydogan, Osman El-Atwani, Ramprashad TI Premier Nanohardness Prabhakaran, Md Ershadul Alam, Nathan Bailey, Jens Darsell, Xiao Li, Aishani Sharma, Mychailo Toloczko, Dalong Zhang |
| On-Site Speaker (Planned) |
Stuart Andrew Maloy |
| Abstract Scope |
The Advanced Fuels Campaign, a key component of the Department of Energy’s Nuclear Energy Fuel Cycle Research and Development program, is advancing the qualification of metallic fuels for fast reactor applications. This effort requires the development and testing of new fuels and cladding materials capable of achieving high burnup levels (>20%) while enduring extreme radiation doses (>200 displacements per atom, dpa) in contact with coolant and fuel. Building on prior research with tempered martensitic steels such as HT9 irradiated to 155 dpa, recent experiments have extended materials testing to doses as high as 240 dpa. In parallel, novel ferritic/martensitic and ferritic Oxide Dispersion Strengthened alloys are being developed through advanced manufacturing techniques to enhance radiation tolerance. This research highlights significant progress in both high-dose irradiated materials testing and the development of next-generation cladding. These advancements contribute to the development and qualification of materials for the extreme conditions of fast reactors. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Mechanical Properties, Environmental Effects |