Publications of T. Schwarz-Selinger
All genres
Talk (215)
261.
Talk
Beneficial Deuterium Retention Properties of Tungsten Heavy Alloy. 15th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials (HWS-15), Virtual (submitted)
262.
Talk
Liquid tin interaction with deuterium plasmas. DPG-Frühjahrstagung der Fachverbände Physik der Hadronen und Kerne, Plasmaphysik und des Arbeitskreises Beschleunigerphysik
, Mainz, Virtual (submitted)
263.
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)
264.
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)
265.
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)
266.
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)
267.
Talk
Accelerated Lifetime Tests of ITER-like Tungsten Monoblocks in Magnum-PSI. 28th IAEA Fusion Energy Conference (FEC 2020), Virtual (submitted)
268.
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)
269.
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)
270.
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)
271.
Talk
Saturation of defect densities at elevated temperature in displacement-damaged tungsten. 20th International Conference on Fusion Reactor Materials (ICFRM-20), Virtual (submitted)
272.
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)
273.
Talk
Fuel removal: complementary research at the TOMAS experimental facility. 15th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials (HWS-15), Virtual (2021)
274.
Talk
Deuterium retention and dislocation structure of tungsten irradiated by different ions. 5th International Workshop Models and Data for Plasma-Material Interaction in Fusion Devices (MoD-PMI 2021) (virtual), Jülich (submitted)
275.
Talk
Solving the Brittleness Problem of Tungsten – Tungsten Fibrereinforced Tungsten Composites. TMS 2021 Virtual Annual Meeting & Exhibition, Virtual (submitted)
276.
Talk
Solving the Brittleness Problem of Tungsten – Tungsten Fibrereinforced Tungsten Composites. TMS2021 - Composite Materials for Nuclear Applications, Virtual (submitted)
277.
Talk
Saturation of defect densities in displacement-damaged tungsten. 18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18), Virtual (submitted)
278.
Talk
Sputtering of EUROFER: The Role of Roughness. 3rd Research Coordination Meeting of CRP on "Plasma-wall Interaction with Reduced-activation Steel Surfaces in Fusion Devices (2015-2020)", Vienna (submitted)
279.
Talk
Behavior of Tin under Low-Temperature Deuterium Plasma Irradiation. 24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 24) (virtual), Jeju (submitted)
280.
Talk
Influence of He concentration and He bubbles on deuterium retention and transport in the bulk of tungsten. 17th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-17), Eindhoven (submitted)