Examination of surface stability of dispersion-strengthened tungsten divertor plasma exposure in DIII-D
2024 Research Campaign, Thrust: FPP Candidate Wall Materials
Purpose of Experiment
This experiment will compare the surface stability of Dispersion-Strengthened Tungsten (DSW) materials in a heated tokamak divertor environment, with standard and helium implanted DSW samples previously tested on DIII-D at ambient temperature. (MP 2024-2502). Tungsten will be dispersion-strengthened with TiC, TaC, and ZrC nanoparticles and consolidated via spark-plasma sintering. Surface stability will be evaluated via crack propagation and recrystallization, and in-situ sputtering measurements.