Publications of T. Schwarz-Selinger
All genres
Talk (220)
261.
Talk
Giraffe – Mechanical testing with in-situ irradiation. The Nuclear Materials Conference (NuMat 2022), Ghent (submitted)
262.
Talk
Influence of hydrogen isotopes on displacement damage formation in EUROFER. 19th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-19), Bonn (submitted)
263.
Talk
Possible defect stabilization due to simultaneous D plasma exposure during annealing in self-ion damaged W. IAEA Technical Meeting on the Effects of Hydrogen Supersaturation and Defect Stabilization in Nuclear Fusion Reactor, Aix-en-Provence (submitted)
264.
Talk
Fuel Retention in and Removal from Neutron-irradiated Tungsten. 18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18), Virtual (submitted)
265.
Talk
Diffusivity and solubility of protium and deuterium in tungsten derived from a combined experimental and modelling approach. 15th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials (HWS-15), Virtual (submitted)
266.
Talk
Influence of Thin Surface Oxide Films on Deuterium Release from Tungsten. 15th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials (HWS-15), Virtual (submitted)
267.
Talk
Effects of thin surface oxide films on deuterium uptake and release from ion-damaged tungsten. DPG-Frühjahrstagung der Fachverbände Physik der Hadronen und Kerne, Plasmaphysik und des Arbeitskreises Beschleunigerphysik
, Mainz, Virtual (submitted)
268.
Talk
Beneficial Deuterium Retention Properties of Tungsten Heavy Alloy. 15th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials (HWS-15), Virtual (submitted)
269.
Talk
Liquid tin interaction with deuterium plasmas. DPG-Frühjahrstagung der Fachverbände Physik der Hadronen und Kerne, Plasmaphysik und des Arbeitskreises Beschleunigerphysik
, Mainz, Virtual (submitted)
270.
Talk
The effect of surface and bulk microstructure on deuterium transport in displacement damaged tungsten. IAEA Technical Meeting on Nuclear Fusion Fuel Permeation in Reactor First Wall Components, Vienna, Virtual (2021)
271.
Talk
Defect stabilisation in tungsten during simultaneous D loading and displacement damage creation: importance for fuel retention and transport in DEMO. 18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18), Virtual (submitted)
272.
Talk
Effect of D on the evolution of displacement damage in W during annealing to 1000 K. 15th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials (HWS-15), Virtual (submitted)
273.
Talk
Basic Data for NRA and Best Practises for IBA. 1st Research Coordination Meeting of the CRP on “Development and Application of Ion Beam Techniques for Materials Irradiation and Characterization Relevant to Fusion Technology” (Virtual), Vienna (submitted)
274.
Talk
Accelerated Lifetime Tests of ITER-like Tungsten Monoblocks in Magnum-PSI. 28th IAEA Fusion Energy Conference (FEC 2020), Virtual (submitted)
275.
Talk
Effect of elevated temperature and D presence on defect creation in W. 5th International Workshop Models and Data for Plasma-Material Interaction in Fusion Devices (MoD-PMI 2021) (virtual), Jülich (2021)
276.
Talk
Influence of the initial D concentration on damage stabilization during selfdamaging of tungsten. 15th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials (HWS-15), Virtual (submitted)
277.
Talk
Understanding Retention and Transport of Hydrogen in Displacement-damaged Tungsten. Seminar: NOMATEN Centre of Excellence in Multifunctional Materials for Industrial and Medical Applications, Virtual (submitted)
278.
Talk
Saturation of defect densities at elevated temperature in displacement-damaged tungsten. 20th International Conference on Fusion Reactor Materials (ICFRM-20), Virtual (submitted)
279.
Talk
Radiation damaging of tungsten: Recent advances in predicting tritium retention and transport for DEMO. 25th International Conference on Plasma Surface Interaction in Controlled Fusion Devices (PSI 25), Jeju (submitted)
280.
Talk
Fuel removal: complementary research at the TOMAS experimental facility. 15th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials (HWS-15), Virtual (2021)