Refractory metals as structural materials for fusion high heat flux components
Tungsten is the favoured armour material for plasma facing components for future fusion
reactors, but studies examining the use of tungsten or other refractory metals in the …
reactors, but studies examining the use of tungsten or other refractory metals in the …
A prospect of using ternary W-5 wt% V-5 wt% Ta alloy manufactured by mechanical alloying and spark plasma sintering as plasma-facing material
H Cui, N Liu, L Luo, Y Xu, J Cheng, Y Wu - Journal of Alloys and …, 2022 - Elsevier
For ensuring W employed as the armor of the divertor component in International
Thermonuclear Experimental Reactor, a ternary W alloy W-5 wt% V-5 wt% Ta was …
Thermonuclear Experimental Reactor, a ternary W alloy W-5 wt% V-5 wt% Ta was …
Helium retention, bubble superlattice formation and surface blistering in helium-irradiated tungsten
The microstructural evolution and helium retention in polycrystalline tungsten (W) implanted
with 100 keV helium ions at different temperatures to a wide range of different fluences were …
with 100 keV helium ions at different temperatures to a wide range of different fluences were …
Low energy Kr5+ ion beam engineering in the optical, structural, surface morphological and electrical properties of RF sputtered TiO2 thin films
Titanium dioxide (TiO 2) thin films were grown on Silicon and glass substrates at room
temperature by RF sputtering deposition technique. All deposited thin films were irradiated …
temperature by RF sputtering deposition technique. All deposited thin films were irradiated …
[HTML][HTML] High-temperature defect recovery in self-ion irradiated W-5 wt% Ta
A study of high-temperature defect recovery has been carried out for W-5 wt% Ta alloy,
irradiated with 2 MeV W+ ions at 500° C, up to 1.2 dpa. After post-irradiation annealing at …
irradiated with 2 MeV W+ ions at 500° C, up to 1.2 dpa. After post-irradiation annealing at …
LIBS study of ITER relevant tungsten–oxygen coatings exposed to deuterium plasma in Magnum-PSI
We discuss the applicability of laser induced breakdown spectroscopy (LIBS) for deuterium
retention analysis in compact and porous tungsten-oxide (WO) coatings. Deuterium loading …
retention analysis in compact and porous tungsten-oxide (WO) coatings. Deuterium loading …
Effect of Ta addition on the fuzz formation of additively manufactured W-based materials
As a divertor plasma-facing material, W will experience high-flux plasma irradiation. In
particular, severe surface morphology change like fuzz formation can be induced by He …
particular, severe surface morphology change like fuzz formation can be induced by He …
Effect of ELM pacing on morphology evolution and erosion of tungsten as a plasma-facing material in a fusion environment
Mitigation of transient plasma events in a future fusion device is necessary to minimize
thermal damage on surrounding plasma facing components (PFCs). Intense heat loading …
thermal damage on surrounding plasma facing components (PFCs). Intense heat loading …
The effect of W2+ irradiation and He+ exposure on W-Ta alloy fabricated via SPS
C Wu, J Du, P Wen, J Tang, T Zhao, J Chen… - Fusion Engineering and …, 2024 - Elsevier
Tungsten (W) has been selected as the material for the divertor in ITER due to its good
thermal and mechanical properties, and alloying of tungsten has been considered as a …
thermal and mechanical properties, and alloying of tungsten has been considered as a …
Influence of W content on microstructure and surface morphology of hard Ni-W films fabricated by magnetron co-sputtering
Due to their unique mechanical, tribological, thermal, and anticorrosion properties, nickel-
tungsten (Ni-W) alloy films have become indispensable for many industrial applications. The …
tungsten (Ni-W) alloy films have become indispensable for many industrial applications. The …