Asociación Centro Tecnológico Ceit (CEIT)
Centro / Instituto vinculado a la Universidad de Navarra
Forschungszentrum Jülich
Jülich, AlemaniaPublicaciones en colaboración con investigadores/as de Forschungszentrum Jülich (19)
2024
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Mock-ups fabrication by HRP technology with advanced W-alloy monoblocks for DEMO divertor target
Fusion Engineering and Design, Vol. 201
2020
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Microstructure, oxidation behaviour and thermal shock resistance of self-passivating W-Cr-Y-Zr alloys
Nuclear Materials and Energy, Vol. 24
2018
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Self-passivating tungsten alloys of the system W-Cr-Y for high temperature applications
International Journal of Refractory Metals and Hard Materials, Vol. 73, pp. 29-37
2017
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Advanced materials for a damage resilient divertor concept for DEMO: Powder-metallurgical tungsten-fibre reinforced tungsten
Fusion Engineering and Design, Vol. 124, pp. 964-968
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Self-passivating W-Cr-Y alloys: Characterization and testing
Fusion Engineering and Design, Vol. 124, pp. 1118-1121
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Smart alloys for a future fusion power plant: First studies under stationary plasma load and in accidental conditions
Nuclear Materials and Energy, Vol. 12, pp. 1363-1367
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Smart tungsten alloys as a material for the first wall of a future fusion power plant
Nuclear Fusion, Vol. 57, Núm. 6
2016
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Advanced tungsten materials for plasma-facing components of DEMO and fusion power plants
Fusion Engineering and Design, Vol. 109-111, pp. 1046-1052
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Manufacturing and testing of self-passivating tungsten alloys of different composition
Nuclear Materials and Energy, Vol. 9, pp. 422-429
2013
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A brief summary of the progress on the EFDA tungsten materials program
Journal of Nuclear Materials, Vol. 442, Núm. 1-3 SUPPL.1
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Recent progress in research on tungsten materials for nuclear fusion applications in Europe
Journal of Nuclear Materials, Vol. 432, Núm. 1-3, pp. 482-500
2011
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Review on the EFDA programme on tungsten materials technology and science
Journal of Nuclear Materials
2009
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High heat flux testing of TiC-doped isotropic graphite for plasma facing components
Advanced Materials Research
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Manufacturing and high heat-flux testing of brazed actively cooled mock-ups with Ti-doped graphite and CFC as plasma-facing materials
Physica Scripta T
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Ti-doped isotropic graphite: A promising armour material for plasma-facing components
Journal of Nuclear Materials, Vol. 386-388, Núm. C, pp. 801-804
2007
1997
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High-heat-flux loading of tungsten coatings on graphite deposited by plasma spray and physical vapor deposition
Fusion Technology, Vol. 32, Núm. 2, pp. 263-275
1996
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The tungsten divertor experiment at ASDEX Upgrade
Plasma Physics and Controlled Fusion, Vol. 38, Núm. 12A
1993
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Influence of Oxygen Partial Pressure on the Quasi‐Ternary System Cr─Mn─Ti Oxide
Journal of the American Ceramic Society, Vol. 76, Núm. 11, pp. 2869-2878