| About this Abstract |
| Meeting |
2020 TMS Annual Meeting & Exhibition
|
| Symposium
|
Radiation Effects in Metals and Ceramics
|
| Presentation Title |
H-41: Elucidating the Role of Dispersoids on the Bulk and Nano-mechanical Properties of Dispersion-strengthened W Alloys Following Ion Irradiation with In-situ Characterization |
| Author(s) |
Eric J. Lang, Quentin Rizzardi, Robert Maass, Jean Paul Allain |
| On-Site Speaker (Planned) |
Eric J. Lang |
| Abstract Scope |
Tungsten (W) is the plasma-facing material of choice for future plasma-burning tokamak fusion devices for its high melting point and high sputter threshold. However, monolithic W is intrinsically brittle and its low recrystallization temperature poses complications in fusion environments. In this work, dispersion-strengthened W samples are processed via spark plasma sintering with TiC, ZrC, and TaC dispersoids alloyed from 0.5 to 10 wt. % to synthesize fine-grained W alloys with inter- and intra-granular dispersoids strengthening the W matrix. The effect of the dispersoid microstructure on the mechanical performance is systematically studied. Bulk studies elucidate greater recrystallization inhibition and ductility than pure W. Nano-mechanical response is studied via in-situ SEM techniques. Nanoindentation and micro-pillar compression is studied to extract stress-strain relations and understand dispersoid-microstructure stability. Correlations with irradiation parameters including: low energy, high temperature D/He ion irradiation will elucidate the synergy between ion damage and nano-mechanical response. |
| Proceedings Inclusion? |
Planned: Supplemental Proceedings volume |