Mechanical properties of tungsten: Recent research on modified tungsten materials in Japan
S Nogami, A Hasegawa, M Fukuda, M Rieth… - Journal of Nuclear …, 2021 - Elsevier
There remain some drawbacks of mechanical properties of W materials as a plasma facing
material (PFM) for fusion reactor divertors, which are low temperature brittleness, high …
material (PFM) for fusion reactor divertors, which are low temperature brittleness, high …
Baseline high heat flux and plasma facing materials for fusion
Y Ueda, K Schmid, M Balden, JW Coenen… - Nuclear …, 2017 - iopscience.iop.org
In fusion reactors, surfaces of plasma facing components (PFCs) are exposed to high heat
and particle flux. Tungsten and Copper alloys are primary candidates for plasma facing …
and particle flux. Tungsten and Copper alloys are primary candidates for plasma facing …
[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 …
fusion reaction and external heating must be exhausted through the narrow area of the …
Development of advanced high heat flux and plasma-facing materials
Plasma-facing materials and components in a fusion reactor are the interface between the
plasma and the material part. The operational conditions in this environment are probably …
plasma and the material part. The operational conditions in this environment are probably …
[HTML][HTML] Use of tungsten material for the ITER divertor
T Hirai, S Panayotis, V Barabash, C Amzallag… - Nuclear Materials and …, 2016 - Elsevier
Since the ITER divertor design includes tungsten monoblocks in the vertical target where
heat loads are maximal, the design to protect leading edges as well as technology R&D for …
heat loads are maximal, the design to protect leading edges as well as technology R&D for …
[HTML][HTML] Additive manufacturing of pure tungsten by means of selective laser beam melting with substrate preheating temperatures up to 1000∘ C
The preferred plasma-facing material in present-day and future magnetic confinement
thermonuclear fusion devices is tungsten. This material is mainly chosen because of its high …
thermonuclear fusion devices is tungsten. This material is mainly chosen because of its high …
The influence of plasma-surface interaction on the performance of tungsten at the ITER divertor vertical targets
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 …
to high fluxes of low-energy particles (eg H, D, T, He, Ne and/or N). Combined with long …
Physics conclusions in support of ITER W divertor monoblock sha**
The key remaining physics design issue for the ITER tungsten (W) divertor is the question of
monoblock (MB) front surface sha** in the high heat flux target areas of the actively cooled …
monoblock (MB) front surface sha** in the high heat flux target areas of the actively cooled …
Conceptual design study for heat exhaust management in the ARC fusion pilot plant
The ARC pilot plant conceptual design study has been extended beyond its initial scope [BN
Sorbom et al., FED 100 (2015) 378] to explore options for managing∼ 525 MW of fusion …
Sorbom et al., FED 100 (2015) 378] to explore options for managing∼ 525 MW of fusion …
DEMO divertor limitations during and in between ELMs
Operation of DEMO in comparison to ITER will be significantly more demanding, as various
additional limitations of physical and technical nature have to be respected. In particular a …
additional limitations of physical and technical nature have to be respected. In particular a …