Publikationen von F. Koch

Adelhelm, C.; Levchuk, D.; Maier, H.; Koch, F.; Ertl, K.: Ceramic Coatings as Tritium Permeation Barriers. Fachbeirat, Garching (2008)

Koch, F.; Bolt, H.: Self passivating ternary and quaternary W-alloys as plasma-facing materials for fusion reactors. 1st International Conference on New Materials for Extreme Environments (ExtreMat), San Sebastian (2008)

Koch, F.; Bolt, H.: Self Passivating W-based Alloys as Plasma Facing Materials for Nuclear Fusion. 11th International Workshop on Plasma-Facing Materials and Components for Fusion Applications (PFMC-11), Greifswald (2006)

Koch, F.; Nocentini, R.; Heinemann, B.; Lindig, S.; Junghanns, P.; Bolt, H.: MoS₂ coatings for the narrow support elements of the W-7X non planar coils. 24th Symposium on Fusion Technology (SOFT 2006), Warsaw (2006)

Levchuk, D.; Koch, F.; Maier, H.; Bolt, H.; Suzuki, A.: Erbium oxide as a new promising tritium permeation barrier. 12th International Conference on Fusion Reactor Materials (ICRFM-12), Santa Barbara,CA (2005)

Maier, H.; Levchuk, D.; Koch, F.; Köck, T.; Bolt, H.: Tritium Permeation Barrier for the First Wall of a Fusion Reactor. 12th International Conference on Fusion Reactor Materials (ICRFM-12), Santa Barbara,CA (2005)

Sawada, A.; Pint, B. A.; Suzuki, A.; Koch, F.; Maier, H.; Terai, T.; Muroga, T.: Long Term Stability of Erbium Oxide Coatings. 12th International Conference on Fusion Reactor Materials (ICRFM-12), Santa Barbara,CA (2005)

Suzuki, A.; Sawada, A.; Koch, F.; Maier, H.; Terai, T.; Muroga, T.: Research on Calcium Zirconate as a Insulating Coatien for Li Blanket Suzuki ICFRM. 12th International Conference on Fusion Reactor Materials (ICFRM-12), Santa Barbara, CA (2005)

Heinemann, B.; Gasparotto, M.; Damiani, C.; Fröschle, M.; Giesen, B.; Holtum, D.; Junghanns, P.; Koch, F.; Lindig, S.; Lingertat, J. et al.; Mendelevitch, B.; Panin, A.; Riedl, R.: Design of Narrow Support Elements for Non Planar Coils of Wendelstein 7-X. 21st IEEE/NPSS Symposium on Fusion Engineering (SOFE), Knoxville,TN (2005)

Brinkmann, J.; Koch, F.; Linsmeier, C.: Oxidation behavior and plasma-wall interaction of tungsten alloys for use as plasma facing material in future fusion devices. HEPP Kolloquium 2013

Bolt, H.; Balden, M.; Koch, F.; Jacob, W.: Oberflächentechnik. Vorlesung: Vorlesung (SS 2009), Technische Universität München