About this Abstract |
| Meeting |
Materials in Nuclear Energy Systems (MiNES) 2025
|
| Symposium
|
Materials in Nuclear Energy Systems (MiNES) 2025
|
| Presentation Title |
Low Temperature Testing of HT-9 After Neutron Irradiation to Very High Doses |
| Author(s) |
Stuart Andrew Maloy, Mychailo Toloczko, Eda Aydogan, Ramprashad Prabhakaran, Nathan Bailey, Tarik Saleh, Bruce Hilton, Andrew Peterson |
| On-Site Speaker (Planned) |
Stuart Andrew Maloy |
| Abstract Scope |
The Advanced Fuels Campaign (AFC) Program under the Department of Energy’s Nuclear Energy Fuel Cycle Research & Development (FCRD) has significant experience at qualifying metallic fuels for fast reactor applications. In this process, new fuels and cladding materials must be developed and tested to high burnup levels (e.g. >20%) requiring cladding to withstand very high doses (greater than 200 dpa) while in contact with the coolant and the fuel. Previous research has been performed on tempered martensitic steels such as HT9 to doses up to 155 dpa. Striving to obtain more data on the effects of neutron irradiation on materials properties of HT9 to higher doses at irradiation temperatures from 350 to 600C, a collaboration was started with TerraPower LLC. In this collaboration, specimens previously irradiated in the Fast Flux Test Facility (FFTF) were shipped to the Research Institute of Atomic Reactors to be irradiated in their BOR-60 reactor to higher doses at similar irradiation temperatures. In this study, testing was performed on HT-9 after irradiation at temperatures at or below 400°C. Total doses accumulated were up to 182 dpa. Specimens were also tested at lower doses after irradiation in FFTF and will be compared to this higher dose data. |
| Proceedings Inclusion? |
Undecided |