Publikationen von T. Schwarz-Selinger
Alle Typen
Vortrag (205)
221.
Vortrag
Electron screening in palladium. 28th International Nuclear Physics Conference (INPC 2022), Cape Town (eingereicht)
222.
Vortrag
Experimental Determination of Irradiation-Induced Stress Relaxation in Thin Tungsten Wires. 86. Jahrestagung der DPG und DPG-Frühjahrstagung der Sektion Materie und Kosmos (SMuK), Dresden (eingereicht)
223.
Vortrag
Fusion Materials Research with the GIRAFFE Experiment – Mechanical Testing under Fusion-Relevant Loads. International Conference on Processing & Manufacturing of Advanced Materials (Thermec 2023), Vienna (eingereicht)
224.
Vortrag
Early stages of He cluster formation in pristine and displacement-damaged tungsten. 86. Jahrestagung der DPG und DPG-Frühjahrstagung der Sektion Materie und Kosmos (SMuK), Dresden (eingereicht)
225.
Vortrag
The influence of displacement damage on helium interaction with and retention in tungsten. 26. Deutsche Physikerinnentagung – 26th German Conference of Women in Physics, Karlsruhe (eingereicht)
226.
Vortrag
Liquid tin interaction with deuterium plasmas. 18th International Conference on Diffusion in Solids and Liquids (DSL 2022), Florence (eingereicht)
227.
Vortrag
The influence of D presence on defect creation during displacement damaging of tungsten. IAEA Technical Meeting on the Effects of Hydrogen Supersaturation and Defect Stabilization in Nuclear Fusion Reactor, Aix-en-Provence (eingereicht)
228.
Vortrag
Comparing high-dose simulated irradiation in tungsten to experiments. COSIRES 2022: 15th Conference on COmputer Simulation of IRradiation Effects in Solids, Porquerolles (2022)
229.
Vortrag
Recent Progress in the Development of Tungsten Fibre-reinforced Tungsten Composite. TMS 2023 Annual Meeting & Exhibition, San Diego, CA (eingereicht)
230.
Vortrag
Giraffe – Mechanical testing with in-situ irradiation. The Nuclear Materials Conference (NuMat 2022), Ghent (eingereicht)
231.
Vortrag
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 (eingereicht)
232.
Vortrag
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 (eingereicht)
233.
Vortrag
Fuel Retention in and Removal from Neutron-irradiated Tungsten. 18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18), Virtual (eingereicht)
234.
Vortrag
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 (eingereicht)
235.
Vortrag
Influence of Thin Surface Oxide Films on Deuterium Release from Tungsten. 15th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials (HWS-15), Virtual (eingereicht)
236.
Vortrag
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 (eingereicht)
237.
Vortrag
Beneficial Deuterium Retention Properties of Tungsten Heavy Alloy. 15th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials (HWS-15), Virtual (eingereicht)
238.
Vortrag
Liquid tin interaction with deuterium plasmas. DPG-Frühjahrstagung der Fachverbände Physik der Hadronen und Kerne, Plasmaphysik und des Arbeitskreises Beschleunigerphysik
, Mainz, Virtual (eingereicht)
239.
Vortrag
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)
240.
Vortrag
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 (eingereicht)