Publikationen von K. Schmid

Vortrag (119)

261.
Vortrag
Doerner, R.; Baldwin, M.; Hanna, J.; Nishijima, D.; Pugno, R.; Roth, J.; Schmid, K.; Wiltner, A.: A Synopsis of PISCES-B Mixed-Material Investigations using Be/C/W. 11th Plasma-Facing Materials and Components for Fusion Applications (PFMC-11), Greifswald (2006)
262.
Vortrag
Kallenbach, A.; Dux, R.; Harhausen, J.; Maggi, C. F.; Neu, R.; Pütterich, T.; Rohde, V.; Schmid, K.; Wolfrum, E.; ASDEX Upgrade Team: Spectroscopic investigation of carbon migration with tungsten walls in ASDEX Upgrade. 17th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 17), Hefei Anhui (2006)
263.
Vortrag
Linsmeier, C.; Ertl, K.; Roth, J.; Wiltner, A.; Schmid, K.; Kost, F.; Bhattacharyya, S.; Baldwin, M.; Doerner, R.: Binary beryllium-tungsten mixed materials. 17th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 17), Hefei Anhui (2006)
264.
Vortrag
Schmid, K.; Krieger, K.; Loarte, A.; Kukushkin, A.; Coster, D.: DIVIMP modelling of tungsten impurity transport in ITER. 17th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 17), Hefei Anhui (2006)
265.
Vortrag
Schmid, K.: Influence of surface defects on high flux sputter erosion. Symposium on Surface Science 2006, St. Christoph am Arlberg (2006)
266.
Vortrag
Schmid, K.: Beryllium Layer Deposition on Carbon and Tungsten from Beryllium Seeded Plasmas. 7th IEA International Workshop on Beryllium Technology, Santa Barbara,CA (2005)
267.
Vortrag
Schmid, K.; Baldwin, M.; Doerner, R.: Beryllium experiments on PISCES. JET Workshop "Options for Testing an ITER Relevant Wall in JET", Culham (2004)
268.
Vortrag
Schmid, K.; Baldwin, M.; Doerner, R.: Influence of Beryllium plasma seeding on the erosion of Carbon. 16th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 16), Portland, Maine (2004)
269.
Vortrag
Schmid, K.: Erosion of carbon by simultaneous impact of deuterium and beryllium and enhanced erosion of Be at elevated temperatures. 11th European Fusion Physics Workshop, Heraklion (2003)
270.
Vortrag
Doerner, R. P.; Baldwin, M. J.; Schmid, K.: The influence of a beryllium containing plasma on the erosion properties of graphite. 10th International Workshop on Carbon Materials for Fusion Application, Jülich (2003)
271.
Vortrag
Schmid, K.: Erosion of high-Z metals with typical impurity ions. 15th Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 15), Gifu (2002)
272.
Vortrag
Schmid, K.: Comparison of surface modification and erosion of high-Z metals due to carbon ion implantation. 12th International Conference on Surface Modification of Materials by Ion Beams (SMMIB), Marburg (2001)

Poster (90)

273.
Poster
Albarodi, A.; Schwarz-Selinger, T.; Schmid, K.: In-situ Uptake Measurement of Deuterium Atoms in Self Damaged Tungsten at Different Temperatures. DPG-Frühjahrstagung 2024, Greifswald (eingereicht)
274.
Poster
Romazanov, J.; Kirschner, A.; Rode, S.; Baumann, C.; Brezinsek, S.; Navarro, M.; Xie, H.; Pitts, R. A.; Wiesen, S.; Groth, M. et al.; Kumpulainen, H.; Effenberg, F.; Schmid, K.; Dittmar, T.; Wüst, E.; Kawan, C.; Wang, E.; Linsmeier, C.: Validation of the ERO2.0 Code Using W7-X and JET Experiments and Predictions for ITER Operation. 29th IAEA Fusion Energy Conference (FEC 2023), London (eingereicht)
275.
Poster
Schmid, K.; Schwarz-Selinger, T.; Arredondo, R.; Theodorou, A.; Pomella Lobo, T.: Implications of T Loss in First Wall Armor and Structural Materials on T-Self-Sufficiency in Future Burning Fusion Devices. 29th IAEA Fusion Energy Conference (FEC 2023), London (eingereicht)
276.
Poster
Zibrov, M.; Schmid, K.; Schwarz-Selinger, T.; Chrominski, W.; Ciupinski, L.: Comparison Deuterium Trapping by Voids and Helium Bubbles in Tungsten: Experiments and Simulations. International Hydrogen Conference, Park City, UT (eingereicht)
277.
Poster
Zibrov, M.; Schmid, K.; Schwarz-Selinger, T.; Chrominski, W.; Ciupinski, L.: Comparison of deuterium trapping by voids and helium bubbles in tungsten. 21st International Conference on Fusion Reactor Materials (ICFRM-21), Granada (eingereicht)
278.
Poster
Arredondo, R.; Manhard, A.; Schmid, K.; Sand, P.: Ion-driven permeation of deuterium in W/EUROFER layer systems at TAPAS. 20th International Conference on Fusion Reactor Materials (ICFRM-20), Virtual (eingereicht)
279.
Poster
Brezinsek, S.; Romazanov, J.; Mayer, M.; Schmid, K.; Dittmar, T.; Dhard, C. P.; Kirschner, A.; Naujoks, D.; Zhao, D.; Wang, E.: Study of global carbon migration in Wendelstein 7-X utilising 13CH4 injection from the island divertor and ERO2.0 modelling. 18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18), Virtual (eingereicht)
280.
Poster
Szabo, P. S.; Kantre, K.; Moro, M. V.; Cupak, C.; Zendejas Medina, L.; Stadlmayr, R.; Schmid, K.; Primetzhofer, D.; Aumayr, F.: In-situ Investigation of Deuterium Retention in Tungsten with Ion Beam Analysis and Thermal Desorption Spectroscopy. 24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 24) (virtual), Jeju (2021)
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