Publications of M. Krychowiak
All genres
Poster (144)
281.
Poster
Assessment of NII line ratio method for analysis of nitrogen enrichment in the W7-X divertor. DPG-Frühjahrstagung der Fachverbände Physik der Hadronen und Kerne, Plasmaphysik und des Arbeitskreises Beschleunigerphysik
, Mainz, Virtual (submitted)
282.
Poster
: Assessment of NII line ratio model for analysis of nitrogen enrichment in the W7-X divertor. 25th International Conference on Plasma Surface Interaction in Controlled Fusion Devices (PSI 25), Jeju (submitted)
283.
Poster
: Gaussian Process Tomography of impurity radiation in the detached divertor plasmas of Wendelstein 7-X stellarator. 47th EPS Conference on Plasma Physics, Virtual (submitted)
284.
Poster
: First feedback-controlled divertor detachment in W7-X: experience from TDU operation and prospects for operation with actively cooled divertor. 25th International Conference on Plasma Surface Interaction in Controlled Fusion Devices (PSI 25), Jeju (submitted)
285.
Poster
: Gaussian process tomography of the effective ion charge Zeff from multiple line-integrated bremsstrahlung spectra. 63rd Annual Meeting of the APS Division of Plasma Physics, Pittsburgh, PA (submitted)
286.
Poster
: Investigation of plasma flow stagnation regions for the Wendelstein 7-X magnetic island chain. 25th International Conference on Plasma Surface Interaction in Controlled Fusion Devices (PSI 25), Jeju (submitted)
287.
Poster
: Investigating spectroscopic measurements in W7X seeded detachment experiments with EMC3 simulations. 25th International Conference on Plasma Surface Interaction in Controlled Fusion Devices (PSI 25), Jeju (submitted)
288.
Poster
: Radiation characteristics of detached divertor plasmas in W7-X. 25th International Conference on Plasma Surface Interaction in Controlled Fusion Devices (PSI 25), Jeju (submitted)
289.
Poster
: First Attempt to Quantify the Recycling Neutrals in W7-X by Means of Experiment-model Comparison. 28th IAEA Fusion Energy Conference (FEC 2020), Virtual (submitted)
290.
Poster
: Updates and Future Development of The He/Ne Beam Diagnostic for Line Ratio Spectroscopy in the Island Divertor of Wendelstein 7-X. 62nd Annual Meeting of the APS Division of Plasma Physics, Virtual Edition (submitted)
291.
Poster
: Bayesian inference of Zeff profiles from near-infrared multichannel bremsstrahlung spectrometer by using Gaussian processes at Wendelstein 7-X. 23rd Topical Conference on High Temperature Plasma Diagnostics (HTPD 2020), Virtual (submitted)
292.
Poster
: Plasma-surface Interaction in the Stellarator W7-X: Conclusion Drawn from Operation with Graphite Plasma-Facing Components. 28th IAEA Fusion Energy Conference (FEC 2020), Virtual (submitted)
293.
Poster
: Small, stable plasmas fully decoupled from the PFCs in W7-X. 62nd Annual Meeting of the APS Division of Plasma Physics, Virtual Edition (submitted)
294.
Poster
: Direct 2D Measurements of Parallel Counter-streaming Flows in the W7-X Scrape-off Layer for Attached and Detached Plasmas. 28th IAEA Fusion Energy Conference (FEC 2020), Virtual (submitted)
295.
Poster
: Experimental Indications of High-recycling and the Role of Pressure and Power Dissipation for Detachment at W7-X. 28th IAEA Fusion Energy Conference (FEC 2020), Virtual (submitted)
296.
Poster
: Spectroscopic study of hydrogen particle behaviour in island divertor of W7-X. 47th EPS Conference on Plasma Physics, Virtual (submitted)
297.
Poster
: Plasma Radiation Behavior Approaching High-radiation Scenarios in W7-X. 28th IAEA Fusion Energy Conference (FEC 2020), Virtual (submitted)
298.
Poster
The He/Ne beam diagnostic for line-ratio spectroscopy in the island divertor of Wendelstein 7-X. 3rd European Conference on Plasma Diagnostics (ECPD 2019), Lisbon (submitted)
299.
Poster
: Initial study on global material transport in Wendelstein 7-X: 13CH4 injection into the near-scrape-off layer of the graphite divertor. 17th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-17), Eindhoven (submitted)
300.
Poster
: Development of impurity seeding for divertor power flux handling in Wendelstein 7-X long-pulse scenarios. 19th International Conference on Fusion Reactor Materials (ICFRM-19), La Jolla, CA (submitted)