Publications of T. Schwarz-Selinger

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)

Markelj, S.; Schwarz-Selinger, T.; Jenus, P.; Ivekovic, A.; Novak, S.; Kelemen, M.; Punzon Quijorna, E.; Sestan, A.; Abram, A.: Deuterium retention in displacement damaged tungsten-based samples with tungsten carbide inclusions. 30th International Conference Nuclear Energy for New Europe (NENE 2021), Bled (submitted)

Markelj, S.; Schwarz-Selinger, T.; Pecovnik, M.; Chrominski, W.; Sestan, A.; Zavasnik, J.: Deuterium transport and retention in the bulk of tungsten containing helium: the effect of helium concentration and microstructure. 20th International Conference on Fusion Reactor Materials (ICFRM-20), Virtual (submitted)

Patino, M. I.; Nishijima, D.; Tokitani, M.; Nagata, D.; Schwarz-Selinger, T.; Doerner, R. P.; Baldwin, M. J.; Tynan, G. R.: Material Mixing and Helium Penetration during Helium-induced Fuzz Growth. 18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18), Virtual (submitted)

Simmonds, M.; Schwarz-Selinger, T.; Ghanem, M.; Frankel, I.; Boechler, N.; Patino, M.; Baldwin, M.; Doerner, R.; Tynan, G.: Reduction in defect removal and in thermal diffusivity recovery due to synergistic defect occupation by hydrogen during annealing self-damaged W. 18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18), Virtual (submitted)

Wielunska, B.; Mayer, M.; Schwarz-Selinger, T.; Egger, W.; Ciupinski, L.; Plocinski, T.: Radiation Damage and Deuterium Retention in Tungsten. 20th International Conference on Fusion Reactor Materials (ICFRM-20), Virtual (submitted)

Zito, A.; Schwarz-Selinger, T.; Rohde, V.; Kappatou, A.; Wischmeier, M.: Towards the operation of a high-resolution mass spectrometer for exhaust gas analysis at ASDEX Upgrade. DPG-Tagung der Sektion Materie und Kosmos (SMuK), Virtual (submitted)

Hakola, A.; Likonen, J.; Lahtinen, A.; Vuoriheimo, T.; Groth, M.; Kumpulainen, H.; Balden, M.; Krieger, K.; Schwarz-Selinger, T.; Brezinsek, S. et al.; Kelemen, M.; Markelj, S.; Uccello, A.; Vassallo, E.; Dellasega, D.; Passoni, M.; Sala, M.; Tsitrone, E.; Bernard, E.: Gross and Net Erosion Balance of Plasma-Facing Components in Full-W Tokamaks. 28th IAEA Fusion Energy Conference (FEC 2020), Virtual (submitted)

Kremer, K.; Brucker, M.; Schwarz-Selinger, T.; Jacob, W.: Influence of thin surface oxide films on D uptake, retention and release from W. 18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18), Virtual (submitted)

Liu, M.; Guo, W.; Wang, J.; Yin, H.; Zhu, X.; Cheng, L.; Zhou, H.-B.; Yuan, Y.; De Temmerman, G.; Schwarz-Selinger, T. et al.; Lu, G.-H.: Blister-dominated deuterium retention in tungsten materials exposed to high fluence plasmas. 24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 24) (virtual), Jeju (submitted)

Neu, R.; Kärcher, A.; Riesch, J.; Raumann, L.; Mao, Y.; Almanstötter, P.; Balden, M.; Coenen, J. W.; Hunger, K.; Maier, H. et al.; Manhard, A.; Schwarz-Selinger, T.: Hydrogen retention in tungsten fibre-reinforced tungsten composites. 24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 24) (virtual), Jeju (submitted)

Reinhart, M.; Brezinsek, S.; Coenen, J. W.; Schwarz-Selinger, T.; Schmid, K.; Kirschner, A.; Hakola, A.; van der Meiden, H. J.; Dejarnac, R.; Tsitrone, E. et al.; Doerner, R.; Baldwin, M.; Nishijima, D.: Latest Results of EUROfusion Plasma-Facing Components Research in the Areas of Power Loading, Material Erosion and Fuel Retention. 28th IAEA Fusion Energy Conference (FEC 2020), Virtual (submitted)

Riesch, J.; Coenen, J. W.; Curzadd, B.; Garisson, L.; Gietl, H.; Höschen, T.; Mao, Y.; Pantleon, W.; Raumann, L.; Schwarz-Selinger, T. et al.; Terentyev, D.; Zinovev, A.; Neu, R.: Effects of neutron irradiation on tungsten fibre-reinforced tungsten composites. 31st Symposium on Fusion Technology (SOFT 2020), Virtual Edition (submitted)

Wielunska, B.; Schwarz-Selinger, T.; Mayer, M.; Plocinski, T.; Ciupinski, L.: Dislocation structure of self-damaged tungsten at different damage levels and its correlation to D retention. 18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18), Virtual (submitted)

Burwitz, V. V.; Schwarz-Selinger, T.; Dürbeck, T.; Holzner, G.; Arredondo Parra, R.; Hugenschmidt, C.: Experimental Studies of Helium Diffusion and Trapping in Tungsten. DPG-Frühjahrstagung 2019 der Sektion Kondensierte Materie (SKM), Regensburg (2019)

Chrominski, W.; Ciupinski, L.; Bazarnik, P.; Markelj, S.; Schwarz-Selinger, T.: Temperature effect on the microstructure of tungsten subjected to ions, deuterium and helium exposure. The 22nd Physical Metallurgy and Materials Science Conference: Advanced Materials and Technologies (AMT 2019), Bukowina Tatrzanska (submitted)

Chrominski, W.; Ciupinski, L.; Bazarnik, P.; Markelj, S.; Schwarz-Selinger, T.: TEM investigation on radiation damage in tungsten exposed to simultaneous and sequential W ion damaging and D plasma exposure at 1000K. 2019 E-MRS Fall Meeting and Exhibit, Warsaw (submitted)

Chrominski, W.; Ciupinski, L.; Bazarnik, P.; Markelj, S.; Schwarz-Selinger, T.: Evolution of dislocation structures and D retention under simultaneous W and D ions exposure in tungsten. 19th International Conference on Fusion Reactor Materials (ICFRM-19), La Jolla, CA (submitted)

Dominguez Gutierrez, F. J.; Toussaint, U. v.; Schwarz-Selinger, T.: Material defects quantification and classification in pristine and deuterated W. 17th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-17), Eindhoven (submitted)

Elgeti, S.; Balden, M.; Böswirth, B.; Greuner, H.; Neu, R.; Schwarz-Selinger, T.: W Enrichment by Preferential Sputtering of EUROFER 97 as Actively Cooled Target. 14th International Symposium on Fusion Nuclear Technology (ISFNT-14), Budapest (submitted)