Tungsten as a Plasma-Facing Material
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Publisher
Elsevier
Reference314 articles.
1. A review of recent experiments on W and high Z materials as plasma-facing components in magnetic fusion devices
2. Hydrogenic retention with high-Z plasma facing surfaces in Alcator C-Mod
3. Behaviour of a tungsten coated molybdenum poloidal limiter in FTU tokamak
4. Deuterium retention and surface modification of tungsten macrobrush samples exposed in FTU Tokamak
5. Performance and erosion of a tungsten brush limiter exposed at the TEXTOR tokamak
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1. Impact of helium and hydrogen plasma exposure on surface damage and erosion of tungsten;Nuclear Fusion;2024-01-26
2. Energies and radiative properties of 1s22l2l′ and 1s(2l)22l′ levels in tungsten ion, W70+;International Journal of Modern Physics B;2024-01-22
3. Atomistic insights into the influence of hydrogen on crack propagation in tungsten;Fusion Engineering and Design;2023-12
4. Cracking mechanisms in additively manufactured pure tungsten from printing single tracks, thin walls and cubes;Materials & Design;2023-10
5. Deuterium retention in tungsten, tungsten carbide and tungsten-ditungsten carbide composites;Journal of Nuclear Materials;2023-08
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