| About this Abstract |
| Meeting |
Materials in Nuclear Energy Systems (MiNES) 2021
|
| Symposium
|
Materials in Nuclear Energy Systems (MiNES) 2021
|
| Presentation Title |
Radiation Tolerance of Capacitive Discharge Resistance Welded 14YWT |
| Author(s) |
Calvin R. Lear, Benjamin P Eftink, Hyosim Kim, Matthew M Schneider, Todd E Steckley, Yongqiang Wang, Thomas J Lienert, Stuart A Maloy |
| On-Site Speaker (Planned) |
Calvin R. Lear |
| Abstract Scope |
Advantages in radiation tolerance, creep resistance, and high temperature strength make oxide dispersion strengthened (ODS) ferritic steels promising materials for extreme conditions. Unfortunately, excess heat and localized melting from traditional fusion welding degrades the dispersed oxide particles responsible for these attributes – making ODS components difficult to join. Recent work with solid-state capacitive discharge resistance welding (CDRW) has produced 14YWT-14YWT joints (caps to thin-walled cladding tubes) without changing dispersoids or microstructure near the weld line. Material from these joints was subjected to self-ion (5.0 MeV Fe2+, 600 dpa, 450 °C) and proton (1.5 MeV H+, 0.7 dpa, 300 °C) irradiations, with pre- and post-irradiation microstructure characterized using electron microscopy and mechanically tested using nano-indentation. The accumulation of radiation-induced defects (dislocation loops, void swelling) and the stability of the post-CDRW microstructure (grain structure, dispersoids) were evaluated to ensure that the CDRW process does not degrade pre-existing resistance to radiation-induced microstructural evolution. |
| Proceedings Inclusion? |
Undecided |