Publications of T. Schwarz-Selinger

Poster (190)

421.
Poster
Simmonds, M. J.; Zaloznik, A.; Schwarz-Selinger, T.; Boechler, N.: A rigorous transient grating spectroscopy analysis for probing heavy-ion damaged materials applied to tungsten. 19th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-19), Bonn (submitted)
422.
Poster
Wielunska-Kus, B.; Schwarz-Selinger, T.; Ciupinski, L.: Influence of deuterium on the microstructure in selfirradiated tungsten. 19th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-19), Bonn (submitted)
423.
Poster
Wielunska-Kus, B.; Spychalski, M.; Schwarz-Selinger, T.; Ciupinski, L.: Change of mechanical properties of W-irradiated tungsten. 21st International Conference on Fusion Reactor Materials (ICFRM-21), Granada (submitted)
424.
Poster
Zaloznik, A.; Baldwin, M. J.; Schwarz-Selinger, T.; Tynan, G. R.: Influence of ion flux on deuterium uptake in plasma-exposed tungsten. 19th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-19), Bonn (submitted)
425.
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 (submitted)
426.
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 (submitted)
427.
Poster
Burwitz, V. V.; Kärcher, A.; Mathes, L.; Holzner, G.; Vadrucci, M.; Schwarz-Selinger, T.; Hugenschmidt, C.: Lattice Defects in Tungsten (111) Single-Crystals for Helium Retention Studies Characterized by Positron Annihilation Spectroscopy. 19th International Conference on Positron Annihilation (ICPA 19), Helsinki (2022)
428.
Poster
Feichtmayer, A.; Curzadd, B.; Benthaus, M.; Estermann, S.; Höschen, T.; Riesch, J.; Schwarz-Selinger, T.; Viebke, D.; Neu, R.: The GIRAFFE Experiment – Current Status and Future Developments for Material Testing under Fusion-Relevant Loads. 32nd Symposium on Fusion Technology (SOFT 2022), Dubrovnik, Virtual (submitted)
429.
Poster
Kremer, K. J.; Jacob, W.; Schwarz-Selinger, T.: Deuterium plasma exposure of thin oxide films on tungsten – Oxygen removal and D uptake. 19th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-19), Bonn (submitted)
430.
Poster
Maier, H.; Schwarz-Selinger, T.; Sal, E.; Garcia-Rosales, C.; Hunger, K.; Dürbeck, T.: Deuterium retention in displacement-damaged selfpassivating tungsten alloys. 19th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-19), Bonn (submitted)
431.
Poster
Feichtmayer, A.; Curzadd, B.; Estermann, S.; Fuhr, M.; Höschen, T.; Lürbke, R.; Riesch, J.; Schwarz-Selinger, T.; Viebke, D.; Neu, R.: Investigation of synergistic effects of irradiation damage, hydrogen retention and mechanical loading on tungsten. DPG-Frühjahrstagung der Fachverbände Physik der Hadronen und Kerne, Plasmaphysik und des Arbeitskreises Beschleunigerphysik , Mainz, Virtual (submitted)
432.
Poster
Grisolia, C.; Hodille, E.; Pecovnik, M.; Ialovega, M.; Bernard, E.; Angot, T.; Martin, C.; Ferro, Y.; Layet, J. M.; Sakamoto, R. et al.; Benannoune, S.; Charles, Y.; De Baker, A.; Delaporte-Mathurin, R.; Mougenot, J.; Becquart, C.; Schwarz-Selinger, T.; Barthe, M.-F.; Bisson, R.; Markelj, S.: Modelling of Hydrogen Trapping, Diffusion and Permeation in Tokamak. 28th IAEA Fusion Energy Conference (FEC 2020), Virtual (2021)
433.
Poster
Hess, L.; Mayer, M.; Manhard, A.; Schwarz-Selinger, T.; Dürbeck, T.: 12C(3He,px)14N cross sections for nuclear reaction analysis at energies up to 6 MeV. 25th International Conference on Ion Beam Analysis (IBA 2021) & 17th International Conference on Particle Induce X-ray Emission (PIXE) & International Conference on Secondary Ion Mass Spectrometry (SIMS), Virtual (submitted)
434.
Poster
Kärcher, A.; Burwitz, V. V.; Schwarz-Selinger, T.; Jacob, W.: Early stages of He cluster formation in tungsten single crystals. DPG-Tagung der Sektion Materie und Kosmos (SMuK), Virtual (submitted)
435.
Poster
Kärcher, A.; Burwitz, V. V.; Schwarz-Selinger, T.; Jacob, W.; Mathes, L.; Hugenschmidt, C.: Early stages of He cluster formation in tungsten. DPG-Frühjahrstagung der Fachverbände Physik der Hadronen und Kerne, Plasmaphysik und des Arbeitskreises Beschleunigerphysik , Mainz, Virtual (submitted)
436.
Poster
Kärcher, A.; Burwitz, V. V.; Schwarz-Selinger, T.; Jacob, W.; Mathes, L.; Hugenschmidt, C.: Helium retention in displacement-damaged tungsten at low fluences and low energy. 25th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 25), Jeju (submitted)
437.
Poster
Kelemen, M.; Mutzke, A.; Pelicon, P.; Schwarz-Selinger, T.; Vassallo, E.; Pedroni, M.; Dellasega, D.; Passoni, M.; Romeo, F.; Hakola, A. et al.; Balden, M.; Zaplotnik, R.; Markelj, S.: Effects of surface roughness on sputter yield of Mo under keV D ion bombardment, experiment and SDTrimSP-3D simulations. 18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18), Virtual (submitted)
438.
Poster
Kremer, K.; Schwarz-Selinger, T.; Jacob, W.: Effects of thin surface oxide films on deuterium uptake in self-damaged tungsten – Evidence for permeation barrier effect. DPG-Tagung der Sektion Materie und Kosmos (SMuK), Virtual (submitted)
439.
Poster
Liu, M.; Cheng, L.; Yuan, Y.; Schwarz-Selinger, T.; De Temmerman, G.; Lu, G.-H.: Blister-dominated retention mechanism in tungsten materials exposed to high fluence deuterium plasma. 18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18), Virtual (submitted)
440.
Poster
Maier, H.; Schwarz-Selinger, T.; Sal, E.; Garcia-Rosales, C.; Hunger, K.; Dürbeck, T.; Manhard, A.: Deuterium Retention in Self-Passivating Tungsten Alloy: Effect of Displacement Damage. 20th International Conference on Fusion Reactor Materials (ICFRM-20), Virtual (submitted)
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