Publikationen von K. Ertl
Alle Typen
Vortrag (15)
61.
Vortrag
Binary beryllium-tungsten mixed materials. 17th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 17), Hefei Anhui (2006)
Poster (13)
62.
Poster
Exploring the resolution limits of time-of-flight RBS with heavy ions. 23rd International Conference on Ion Beam Analysis (IBA 2017), Shanghai (eingereicht)
63.
Poster
Deuterium Retention in Self-damaged Tungsten Exposed to High-flux Plasmas. 20th International Conference on Plasma Surface Interactions 2012 (PSI 20), Aachen (2012)
64.
Poster
Deuterium Retention in Tungsten Exposed to High-Flux Plasmas. 15th International Conference of Fusion Reactor Materials (ICFRM-15), Charleston, SC (2011)
65.
Poster
Hydrogen Retention in Tungsten Exposed to High-Flux Plasmas. 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)
66.
Poster
Deuterium retention in various pre-damaged materials as a function of the exposure temperature. 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)
67.
Poster
Trapping of permeating deuterium in defect induced at the rear side of tungsten foil. 19th Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 19), San Diego, CA (2010)
68.
Poster
Deuterium Retention in Pre-irradiated Tungsten Exposed to High-flux Plasma. 19th Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 19), San Diego, CA (2010)
69.
Poster
Preparation and characterization of Er2O3 coatings for fusion applications. 14th International Conference on Fusion Reactor Materials (ICFRM-14), Sapporo (2009)
70.
Poster
Hydrogen retention in tungsten. Fachbeirat, Greifswald (2009)
71.
Poster
Ion-driven deuterium retention in self-damaged tungsten. 12th International Workshop on Plasma-Facing Materials and Components for Fusion Applications (PFMC-12), Jülich (2009)
72.
Poster
Ceramic Coatings as Tritium Permeation Barriers. Fachbeirat, Garching (2008)
73.
Poster
Radiation damage effect on the performance of tritium permeation barriers. 8th International Symposium on Fusion Nuclear Technology (ISFNT-8), Heidelberg (2007)
74.
Poster
Structural investigation of the binary Be-W intermetallic system. 11th International Workshop on Plasma-Facing Materials and Components for Fusion Applications (PFMC-11), Greifswald (2006)
Bericht (1)
75.
Bericht
Analyse der Energieverteilung feldemittierter Elektronen am System Europiumsulfid auf Wolfram. Max-Planck-Institut für Plasmaphysik, Garching (1982), 185 S.