[HTML][HTML] Divertor of the European DEMO: Engineering and technologies for power exhaust

JH You, G Mazzone, E Visca, H Greuner… - Fusion Engineering and …, 2022 - Elsevier
In a power plant scale fusion reactor, a huge amount of thermal power produced by the
fusion reaction and external heating must be exhausted through the narrow area of the …

[HTML][HTML] Recent progress on the R&D of W-ZrC alloys for plasma facing components in fusion devices

R Liu, ZM Xie, JF Yang, T Zhang, T Hao… - Nuclear Materials and …, 2018 - Elsevier
Tungsten is considered as the most promising material for plasma facing components
(PFCs) in the magnetic confinement fusion devices, due to its high melting temperature, high …

The influence of plasma-surface interaction on the performance of tungsten at the ITER divertor vertical targets

G De Temmerman, T Hirai, RA Pitts - Plasma Physics and …, 2018 - iopscience.iop.org
The tungsten (W) material in the high heat flux regions of the ITER divertor will be exposed
to high fluxes of low-energy particles (eg H, D, T, He, Ne and/or N). Combined with long …

Extraordinary high ductility/strength of the interface designed bulk W-ZrC alloy plate at relatively low temperature

ZM Xie, R Liu, S Miao, XD Yang, T Zhang, XP Wang… - Scientific reports, 2015 - nature.com
The refractory tungsten alloys with high ductility/strength/plasticity are highly desirable for a
wide range of critical applications. Here we report an interface design strategy that achieves …

Recrystallization and thermal shock fatigue resistance of nanoscale ZrC dispersion strengthened W alloys as plasma-facing components in fusion devices

ZM Xie, S Miao, R Liu, LF Zeng, T Zhang… - Journal of Nuclear …, 2017 - Elsevier
Recrystallization and thermal shock fatigue resistance behavior of nanoscale ZrC dispersion
strengthened bulk tungsten alloys (W-0.5 wt% ZrC, WZrC) as potential candidates for …

Effect of potassium bubbles on the thermal shock fatigue behavior of large-volume potassium-doped tungsten alloy

X Ma, F Feng, X Zhang, T Wang, X Liu, W Lv… - Nuclear …, 2022 - iopscience.iop.org
A newly developed large-volume potassium-doped tungsten (W–K) plate with a thickness of
15 mm and a weight of 25 kg by powder metallurgy plus hot rolling was prepared to meet the …

High thermal shock resistance of the hot rolled and swaged bulk W–ZrC alloys

ZM Xie, R Liu, S Miao, XD Yang, T Zhang… - Journal of nuclear …, 2016 - Elsevier
The thermal shock (single shot) resistance and mechanical properties of the W–0.5 wt% ZrC
(WZC) alloys manufactured by ordinary sintering followed by swaging or rolling process …

[HTML][HTML] The high thermal stability induced by a synergistic effect of ZrC nanoparticles and Re solution in W matrix in hot rolled tungsten alloy

T Zhang, WY Du, CY Zhan, MM Wang, HW Deng… - Nuclear Engineering …, 2022 - Elsevier
The synergistic effect of ZrC nanoparticle pining and Re solution in W matrix on the thermal
stability of tungsten was studied by investigating the evolution of the microstructure …

Evolution of tungsten degradation under different cyclic ELM-like high heat flux plasma

S Jiang, L Chen, W Li, S Hao, H Shi, X Li - Journal of Nuclear Materials, 2024 - Elsevier
A millisecond pulsed repetitive plasma generator based on capillary discharge is utilized to
produce ELM-like heat load. Based on this device, the evolution of tungsten degradation …

Morphological and structural effects on tungsten targets produced by fusion plasma pulses from a table top plasma focus

MJ Inestrosa-Izurieta, E Ramos-Moore, L Soto - Nuclear Fusion, 2015 - iopscience.iop.org
A table top plasma focus device operating at hundreds of joules was used to simulate an
equivalent damage factor than the obtained on the divertor in tokamak experiments. Using …