Publikationen von C. Garcia-Rosales
Alle Typen
Vortrag (17)
61.
Vortrag
Erosion Processes of Carbon Materials under Hydrogen Bombardment and their Mitigation by Doping. 10th International Workshop on Carbon Materials for Fusion Application, Jülich (2003)
62.
Vortrag
Chemical erosion of carbon materials by hydrogen - Reduction by doping and morphology changes. PISCES, University of California, San Diego,CA (2003)
63.
Vortrag
Chemical erosion of carbon by hydrogen bombardment potential of mitigation by doping.
Poster (10)
64.
Poster
Manufacturing and oxidation behaviour of bulk self-passivating tungsten-based alloys. 11th International Symposium on Fusion Nuclear Technology (ISFNT-11), Barcelona (2013)
65.
Poster
Self-passivating tungsten alloys - Oxidation behaviour of thin films and bulk material. 15th International Conference of Fusion Reactor Materials (ICFRM-15), Charleston, SC (2011)
66.
Poster
Powder metallurgical processing of self-passivating tungsten alloys for fusion first wall application. 15th International Conference of Fusion Reactor Materials (ICFRM-15), Charleston, SC (2011)
67.
Poster
A brief summary of the progress on the EFDA tungsten materials programme. 15th International Conference on Fusion Reactor Materials (ICFRM-15), Charleston, SC (2011)
68.
Poster
Oxidation behaviour of silicon-free tungsten alloys for use as first wall material. 13th International Workshop on Plasma-Facing Materials and Components for Fusion Applications / 1st International Conference on Fusion Energy Materials Science (13th PFMC Workshop / 1st FEMaS Conference), Rosenheim (2011)
69.
Poster
Manufacturing of Self-Passivating W-Cr-Si Alloys by Mechanical Alloying and Hip. 26th Symposium on Fusion Technology (SOFT 2010), Porto (2010)
70.
Poster
Compilation of erosion yields of metal-doped carbon materials by deuterium impact. 14th International Conference on Fusion Reactor Materials (ICFRM-14), Sapporo (2009)
71.
Poster
Chemical sputtering of metal-doped carbon-based materials by deuterium bombardment from ion beam and plasma. 12th International Workshop on Plasma-Facing Materials and Components for Fusion Applications (PFMC-12), Jülich (2009)
72.
Poster
Testing of TiC-doped isotropic graphite under ITER-relevant divertor conditions. 1st International Conference on New Materials for Extreme Environments (ExtreMat), San Sebastian (2008)
73.
Poster
Chemical erosion behaviour of Ti-doped isotropic graphite for plasma facing components. 18th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 18), Toledo (2008)
Bericht (3)
74.
Bericht
Extension of the ASDEX Upgrade Programme: Divertor II and Tungsten Target Plate Experiment Application for Preferential Support, Phase I and II. Proposal. Max-Planck-Institut für Plasmaphysik, Garching (DE) (1994), 140 S.
75.
Bericht
Extension of the ASDEX Upgrade Programme: Divertor II and Tungstein Target Plate Experiment Application for Preferential Support, Phase I and II. Max-Planck-Institut für Plasmaphysik, Garching (DE) (1994), 123 S.
76.
Bericht
Sputtering Data. Max-Planck-Institut für Plasmaphysik, Garching (1993), 342 S.