Publikationen von K. Krieger
Alle Typen
Vortrag (164)
301.
Vortrag
In situ Measurement of H, D, T Retention in the JET Tungsten Divertor Components – Lessons Learned for the ITER LID-QMS Diagnostic. 20th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-20), Ljubljana (eingereicht)
302.
Vortrag
Modelling marker erosion at the divertor region of the ASDEX Upgrade tokamak using the ERO2.0 code. 8th Asia-Pacific Conference on Plasma Physics (AAPPS-DPP 2024), Malacca (eingereicht)
303.
Vortrag
In situ Tritium Retention Diagnostic using Laser-Induced Desorption: JET results and ITER outlook. 33rd Symposium on Fusion Technology (SOFT 2024), Dublin (eingereicht)
304.
Vortrag
Testing of ITER-like Plasma Facing Units in the WEST tokamak: progress in understanding damage mechanisms. 19th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-19), Bonn (2023)
305.
Vortrag
Liquid tin interaction with deuterium plasmas. 49th EPS Conference on Plasma Physics, Bordeaux (eingereicht)
306.
Vortrag
Development of a liquid metal divertor solution for DEMO. 15th International Symposium on Fusion Nuclear Technology (ISFNT-15), Las Palmas de Gran Canaria (eingereicht)
307.
Vortrag
FIB line marking as a tool for local erosion/deposition/fuzz formation measurements in ASDEX Upgrade during the He campaign. 19th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-19), Bonn (eingereicht)
308.
Vortrag
Boronisation with tungsten plasma-facing surfaces in ASDEX Upgrade. 26th International Conference on Plasma Surface Interaction in Controlled Fusion Devices (PSI 26), Marseille (eingereicht)
309.
Vortrag
Performance of a liquid tin divertor target during ASDEX Upgrade L- and H-mode operation. 19th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-19), Bonn (eingereicht)
310.
Vortrag
Cracks initiation and propagation of tungsten actively cooled ITER-like components during high power load experiment in WEST. 19th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-19), Bonn (2023)
311.
Vortrag
Global modelling of helium Plasma-Wall Interaction experiments in ASDEX-Upgrade. 26th International Conference on Plasma Surface Interaction in Controlled Fusion Devices (PSI 26), Marseille (eingereicht)
312.
Vortrag
The Competition between W Nanostructure Formation and W Annealing, W Erosion and Low-Z Co-Deposition in the Divertor of Metallic Fusion Devices. 29th IAEA Fusion Energy Conference (FEC 2023), London (eingereicht)
313.
Vortrag
Inhibited cavitation in lanthanum doped tungsten under multiple melting exposures in GLADIS and ASDEX-Upgrade. 21st International Conference on Fusion Reactor Materials (ICFRM-21), Granada (eingereicht)
314.
Vortrag
Boron redistribution after boron powder injection in ASDEX Upgrade. 25th International Conference on Plasma Surface Interaction in Controlled Fusion Devices (PSI 25), Jeju (eingereicht)
315.
Vortrag
Performance of a liquid tin divertor target during ASDEX Upgrade L- and H-mode operation. 7th International Symposium on Liquid (Metals) Applications for Fusion (ISLA-7), Chubu (eingereicht)
316.
Vortrag
Sustained W-melting on the poloidal leading edge of the actively cooled ITER-like Plasma Facing Units in WEST. 18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18), Virtual (2021)
317.
Vortrag
Development of the MEMOS-U macroscopic melt dynamics code – benchmarking and applications. 18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18), Virtual (eingereicht)
318.
Vortrag
Experiments and modelling on ASDEX Upgrade and WEST in support of tool development for tokamak reactor armour melting assessments. 25th International Conference on Plasma Surface Interaction in Controlled Fusion Devices (PSI 25), Jeju (eingereicht)
319.
Vortrag
Operating ITER grade tungsten plasma facing components in a tokamak environment: overview of WEST first campaigns. 18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18), Virtual (eingereicht)
320.
Vortrag
Impact of Misalignments on ITER-like Plasma Facing Components in WEST Tokamak. 31st Symposium on Fusion Technology (SOFT 2020), Virtual Edition (2020)