Publications of T. Schwarz-Selinger
All genres
Poster (190)
461.
Poster
Inductive heating based apparatus to revise the Frauenfelder data set for hydrogen diffusion in tungsten. 19th International Conference on Fusion Reactor Materials (ICFRM-19), La Jolla, CA (submitted)
462.
Poster
Diffusion of deuterium in tungsten: experiments question familiar assumptions. 17th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-17), Eindhoven (submitted)
463.
Poster
Angular dependence of W and Mo erosion yield studied on textured surfaces with keV D ions. 17th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-17), Eindhoven (submitted)
464.
Poster
Fuel Retention in Tungsten Heavy Alloy. 17th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-17), Eindhoven (submitted)
465.
Poster
Erosion and Deuterium Uptake of Solid and Liquid Tin in a Low-temperature Deuterium Plasma. 17th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-17), Eindhoven (submitted)
466.
Poster
Behaviour of Tin under Low-Temperature Deuterium Plasma Irradiation. 3rd IAEA Technical Meeting on Divertor Concepts, Vienna (submitted)
467.
Poster
Material mixing and He replacement during He bubble formation in W. 17th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-17), Eindhoven (submitted)
468.
Poster
A model for stabilization of defects due to D presence during damage creation by W ion irradiation in tungsten. 17th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-17), Eindhoven (submitted)
469.
Poster
Plasma-deposited amorphous carbon thin films as calibration standards for ion beam analysis. 24th International Conference on Ion Beam Analysis (IBA 2019), Antibes (submitted)
470.
Poster
Radiation damage and deuterium retention in tungsten. 19th International Conference on Fusion Reactor Materials (ICFRM-19), La Jolla, CA (submitted)
471.
Poster
TEM analysis of radiation induced degradation of tungsten. The Nuclear Materials Conference (NuMat 2018), Seattle, WA (submitted)
472.
Poster
Erosion and deposition investigations on Wendelstein 7-X first wall components for the first operation phase in divertor configuration. 30th Symposium on Fusion Technology (SOFT 2018), Giardini Naxos (submitted)
473.
Poster
The effect of hydrogen presence on damage stabilization under simultaneous W ion damaging and D ion exposure. 23rd International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 23), Princeton, NJ (submitted)
474.
Poster
Grain-boundary-induced modification of the surface-bulk migration barrier for hydrogen isotopes in tungsten. 27th International Conference Nuclear Energy for New Europe (NENE 2018), Portoroz (submitted)
475.
Poster
The Influence of Displacement Damage and Helium on Deuterium Transport and Retention in Tungsten. 27th IAEA Fusion Energy Conference (FEC 2018), Gandhinagar (submitted)
476.
Poster
SIESTA: a new high-current ion source for angle-dependent sputter yield measurements. 82. Jahrestagung der DPG und DPG-Frühjahrstagung der Sektion AMOP, Erlangen (submitted)
477.
Poster
Angle-dependent sputter-yield measurements of keV D ions on Fe and W with a new high-current ion source. 23rd International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 23), Princeton, NJ (submitted)
478.
Poster
Influence of Near-surface Blisters on Deuterium Transport in Tungsten: Experiment and Modelling. 16th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-16), Neuss (submitted)
479.
Poster
ERO modelling for Be erosion by Ar and He plasma at PISCES-B. 16th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-16), Neuss (2017)
480.
Poster
Preparation of PFCs for the Efficient Use in ITER and DEMO: Plasma-Wall Interaction Studies within the EUROfusion Consortium. 26th IAEA Fusion Energy Conference (FEC 2016), Kyoto (2017)