| About this Abstract |
| Meeting |
2020 TMS Annual Meeting & Exhibition
|
| Symposium
|
Radiation Effects in Metals and Ceramics
|
| Presentation Title |
Characterizing Self-ion Irradiated Tungsten: Nano-indentation, Multi-technique Microscopy and Crystal-plasticity Modeling |
| Author(s) |
Suchandrima Das, Hongbing Yu, Kenichiro Mizohata, Edmund Tarleton, Felix Hofmann |
| On-Site Speaker (Planned) |
Suchandrima Das |
| Abstract Scope |
Tungsten is the front-runner material for armour components in future fusion reactors. In-service irradiation with fusion neutrons will generate displacement cascades, leaving behind lattice defects. Understanding irradiation-induced evolution of mechanical properties, as a function of dose, is essential to accurately predict component performance and lifetime. Self-ion-implantation provides a convenient approach for mimicking neutron-irradiation damage. Here, we characterise the deformation behaviour of self-ion-implanted tungsten exposed to different damage levels, using nano-indentation, atomic force microscopy, and high-resolution electron backscatter diffraction. <001>-grains of implanted tungsten show increased hardness, pile-up and confined lattice distortions around nano-indents; all of which increase with dose until 0.1 dpa, and saturate thereafter. These observations suggest that dislocation motion is initially obstructed by self-ion-induced defects, but that the obstacle strength is reduced by progressive passage of dislocations, leading to strain-softening. Experimental results are directly compared with 3D crystal plasticity finite element calculations we have developed that capture these effects. |
| Proceedings Inclusion? |
Planned: Supplemental Proceedings volume |