| About this Abstract |
| Meeting |
2021 TMS Annual Meeting & Exhibition
|
| Symposium
|
Composite Materials for Nuclear Applications
|
| Presentation Title |
Evaluation and Irradiation of 14YWT Capacitive Discharge Resistance Welds |
| Author(s) |
Calvin R. Lear, Benjamin Paul Eftink, Hyosim Kim, Todd Edward Steckley, Thomas J Lienert, Stuart Andrew Maloy |
| On-Site Speaker (Planned) |
Calvin R. Lear |
| Abstract Scope |
Oxide dispersion strengthened (ODS) ferritic steels are promising candidates for use in extreme conditions, given their tolerance to radiation, resistance to creep, and maintained strength at high temperatures. However, the dispersoids responsible for these attributes are easily redistributed, agglomerated, and even altered in the prolonged high heat and localized melting of traditional fusion welding. A solid-state capacitive discharge resistance welding (CDRW) technique was used to cap thin walled, small diameter cladding tubes of the ODS alloy 14YWT. Microstructural evolution (e.g., recrystallization, oxide particle stability) in and around these joints was characterized using electron microscopy, while a mix of macro-mechanical testing and nano-indentation were used to probe the ductility and strength of the weld. Further, the most promising samples were irradiated using 5 MeV Fe2+ to a high dose (600 dpa, 450 °C) and characterized using electron microscopy to better understand their long-term stability. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Joining, Mechanical Properties |