Publikationen von M. Krychowiak
Alle Typen
Zeitschriftenartikel (92)
2024
Zeitschriftenartikel
66, 015005 (2024)
Analysis of the neutral fluxes in the divertor region of Wendelstein 7-X under attached and detached conditions using EMC3-EIRENE. Plasma Physics and Controlled Fusion
Zeitschriftenartikel
95, 073524 (2024)
Charge exchange recombination spectroscopy on the alkali beam of Wendelstein 7-X. Review of Scientific Instruments
Zeitschriftenartikel
64, 086027 (2024)
Conditions and benefits of X-point radiation for the island divertor. Nuclear Fusion
Zeitschriftenartikel
64, 076060 (2024)
Heat and particle exhaust in high-performance plasmas in Wendelstein 7-X. Nuclear Fusion
Zeitschriftenartikel
64, 112002 (2024)
Overview of the first Wendelstein 7-X long pulse campaign with fully water-cooled plasma facing components. Nuclear Fusion
Zeitschriftenartikel
39, 101675 (2024)
Migration and balance of 13C in the stellarator Wendelstein 7-X after 13CH4 local injection into the island divertor. Nuclear Materials and Energy
Zeitschriftenartikel
95, 113511 (2024)
Spectral in situ ellipsometer for thin layer measurements in thermonuclear fusion applications. Review of Scientific Instruments
Zeitschriftenartikel
64, 106022 (2024)
Bayesian modelling of multiple plasma diagnostics at Wendelstein 7-X. Nuclear Fusion
Zeitschriftenartikel
64, 086016 (2024)
Validation of the ERO2.0 code using W7-X and JET experiments and predictions for ITER operation. Nuclear Fusion
Zeitschriftenartikel
64, 056042 (2024)
Impurity leakage mechanisms in the Wendelstein 7-X island divertor under friction-dominated conditions. Nuclear Fusion
Zeitschriftenartikel
64, 126047 (2024)
First experimental confirmation of island SOL geometry effects in a high radiation regime on W7-X. Nuclear Fusion 2023
Zeitschriftenartikel
63, 026031 (2023)
Improvement in the simulation tools for heat distribution predictions and control of baffle and middle divertor loads in Wendelstein 7-X. Nuclear Fusion
Zeitschriftenartikel
34, 101363 (2023)
First feedback-controlled divertor detachment in W7-X: Experience from TDU operation and prospects for operation with actively cooled divertor. Nuclear Materials and Energy
Zeitschriftenartikel
4 (1), S. 142 - 151 (2023)
Development of the W7-X Alkali Metal Beam Diagnostic Observation System for OP2. Journal of Nuclear Engineering
Zeitschriftenartikel
37, 101514 (2023)
Performance of tungsten plasma facing components in the stellarator experiment W7-X: Recent results from the first OP2 campaign. Nuclear Materials and Energy
Zeitschriftenartikel
63, 099501 (2023)
Corrigendum: Gas exhaust in the Wendelstein 7-X stellarator during the first divertor operation (2022 Nucl. Fusion 62 096016). Nuclear Fusion
Zeitschriftenartikel
65, 105006 (2023)
Observation of impurity accumulation and its compatibility with high plasma performance in W7-X. Plasma Physics and Controlled Fusion 2022
Zeitschriftenartikel
62, 016006 (2022)
Plasma-surface interaction in the stellarator W7-X: conclusions drawn from operation with graphite plasma-facing components. Nuclear Fusion
Zeitschriftenartikel
33, 101269 (2022)
Bayesian modeling of collisional-radiative models applicable to thermal helium beam plasma diagnostics. Nuclear Materials and Energy
Zeitschriftenartikel
64, 075010 (2022)
Impurity temperatures measured via line shape analysis in the island scrape-off-layer of Wendelstein 7-X. Plasma Physics and Controlled Fusion