Publikationen von T. Schwarz-Selinger
Alle Typen
Poster (190)
441.
Poster
Deuterium Retention in Self-Passivating Tungsten Alloy: Effect of Displacement Damage. 20th International Conference on Fusion Reactor Materials (ICFRM-20), Virtual (eingereicht)
442.
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)
443.
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)
444.
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)
445.
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)
446.
Poster
Radiation Damage and Deuterium Retention in Tungsten. 20th International Conference on Fusion Reactor Materials (ICFRM-20), Virtual (eingereicht)
447.
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)
448.
Poster
Gross and Net Erosion Balance of Plasma-Facing Components in Full-W Tokamaks. 28th IAEA Fusion Energy Conference (FEC 2020), Virtual (eingereicht)
449.
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)
450.
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)
451.
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)
452.
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)
453.
Poster
Effects of neutron irradiation on tungsten fibre-reinforced tungsten composites. 31st Symposium on Fusion Technology (SOFT 2020), Virtual Edition (eingereicht)
454.
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)
455.
Poster
Experimental Studies of Helium Diffusion and Trapping in Tungsten. DPG-Frühjahrstagung 2019 der Sektion Kondensierte Materie (SKM), Regensburg (2019)
456.
Poster
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 (eingereicht)
457.
Poster
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 (eingereicht)
458.
Poster
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 (eingereicht)
459.
Poster
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 (eingereicht)
460.
Poster
W Enrichment by Preferential Sputtering of EUROFER 97 as Actively Cooled Target. 14th International Symposium on Fusion Nuclear Technology (ISFNT-14), Budapest (eingereicht)