Publications of C. Garcia-Rosales
All genres
Journal Article (40)
1.
Journal Article
432 (1-3), pp. 482 - 500 (2013)
Recent progress in research on tungsten materials for nuclear fusion applications in Europe. Journal of Nuclear Materials 2.
Journal Article
442 (1-3), pp. S173 - S180 (2013)
A brief summary of the progress on the EFDA tungsten materials program. Journal of Nuclear Materials 3.
Journal Article
442 (1-3), pp. S181 - S189 (2013)
Recent progress in R&D on tungsten alloys for divertor structural and plasma facing materials. Journal of Nuclear Materials 4.
Journal Article
417 (1-3), pp. 612 - 615 (2011)
Compilation of erosion yields of metal-doped carbon materials by deuterium impact from ion beam and low temperature plasma. Journal of Nuclear Materials 5.
Journal Article
2011 (T145), 014018 (5pp) (2011)
Self-passivating bulk tungsten-based alloys manufactured by powder metallurgy. Physica Scripta 6.
Journal Article
417 (1-3), pp. 463 - 467 (2011)
Review on the EFDA programme on tungsten materials technology and science. Journal of Nuclear Materials 7.
Journal Article
386-388, pp. 801 - 804 (2009)
Ti-doped isotropic graphite: A promising armour material for plasma-facing components. Journal of Nuclear Materials 8.
Journal Article
386-388, pp. 805 - 808 (2009)
Improvement of thermal shock resistance of isotropic graphite by Ti-doping. Journal of Nuclear Materials 9.
Journal Article
16 (10), pp. 34 - 36 (2008)
Pushing the limit. Materials World 10.
Journal Article
T111, pp. 62 - 67 (2004)
Erosion Processes of Carbon Materials under Hydrogen Bombardment and their Mitigation by Doping. Physica Scripta 11.
Journal Article
T103, pp. 38 - 42 (2003)
Deuterium Retention by Implantation in Carbide-Doped Graphites. Physica Scripta 12.
Journal Article
307, pp. 1282 - 1288 (2002)
Improvement of the thermo-mechanical properties of fine grain graphite by doping with different carbides. Journal of Nuclear Materials 13.
Journal Article
17 (5), pp. 2785 - 2790 (1999)
Temperature programmed desorption from graphite. Journal of Vaccum Science and Technology A 14.
Journal Article
241-243, pp. 716 - 721 (1997)
Performance of the Ti Doped Graphite RG-Ti-91 at the Divertor of the Tokamak ASDEX-Upgrade. Journal of Nuclear Materials 15.
Journal Article
37, 10, pp. 1375 - 1393 (1997)
Hydrogen Isotope Inventory in the Graphite Divertor Tiles of ASDEX Upgrade as Measured by Thermal Desorption Spectroscopy. Nuclear Fusion 16.
Journal Article
241-243, pp. 1082 - 1086 (1997)
Hydrogen trapping in and release from tungsten: Modeling and comparison with graphite with regard to its use as fusion reactor material. Journal of Nuclear Materials 17.
Journal Article
32, 2, pp. 263 - 276 (1997)
High-Heat-Flux Loading of Tungsten Coatings on Graphite Deposited by Plasma Spray and Physical Vapour Deposition. Fusion Technology 18.
Journal Article
241-243, pp. 734 - 738 (1997)
Migration of Tungsten Eroded from Divertor Tiles in ASDEX Upgrade. Journal of Nuclear Materials 19.
Journal Article
241-243, pp. 734 - 738 (1997)
Migration of tungsten eroded from divertor tiles in ASDEX Upgrade. Journal of Nuclear Materials 20.
Journal Article
246, 1, pp. 9 - 16 (1997)
Quantitative AMS Depth Profiling of the Hydrogen Isotopes Collected in Graphite Divertor and Wall Tiles of the Tokamak ASDEX-Upgrade. Journal of Nuclear Materials