Publikationen von T. Schwarz-Selinger
Alle Typen
Poster (205)
481.
Poster
Early stages of He cluster formation in tungsten single crystals. DPG-Tagung der Sektion Materie und Kosmos (SMuK), Virtual (eingereicht)
482.
Poster
Early stages of He cluster formation in tungsten. DPG-Frühjahrstagung der Fachverbände Physik der Hadronen und Kerne, Plasmaphysik und des Arbeitskreises Beschleunigerphysik
, Mainz, Virtual (eingereicht)
483.
Poster
Helium retention in displacement-damaged tungsten at low fluences and low energy. 25th International Conference on Plasma Surface Interaction in Controlled Fusion Devices (PSI 25), Jeju (eingereicht)
484.
Poster
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 (eingereicht)
485.
Poster
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 (eingereicht)
486.
Poster
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 (eingereicht)
487.
Poster
Deuterium Retention in Self-Passivating Tungsten Alloy: Effect of Displacement Damage. 20th International Conference on Fusion Reactor Materials (ICFRM-20), Virtual (eingereicht)
488.
Poster
Deuterium retention in displacement damaged tungsten-based samples with tungsten carbide inclusions. 30th International Conference Nuclear Energy for New Europe (NENE 2021), Bled (eingereicht)
489.
Poster
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 (eingereicht)
490.
Poster
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 (eingereicht)
491.
Poster
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 (eingereicht)
492.
Poster
Radiation Damage and Deuterium Retention in Tungsten. 20th International Conference on Fusion Reactor Materials (ICFRM-20), Virtual (eingereicht)
493.
Poster
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 (eingereicht)
494.
Poster
Gross and Net Erosion Balance of Plasma-Facing Components in Full-W Tokamaks. 28th IAEA Fusion Energy Conference (FEC 2020), Virtual (eingereicht)
495.
Poster
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 (eingereicht)
496.
Poster
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 (eingereicht)
497.
Poster
Hydrogen retention in tungsten fibre-reinforced tungsten composites. 24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 24) (virtual), Jeju (eingereicht)
498.
Poster
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 (eingereicht)
499.
Poster
Effects of neutron irradiation on tungsten fibre-reinforced tungsten composites. 31st Symposium on Fusion Technology (SOFT 2020), Virtual Edition (eingereicht)
500.
Poster
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 (eingereicht)