Publikationen von M. Faitsch
Alle Typen
Zeitschriftenartikel (60)
1.
Zeitschriftenartikel
277, 03003 (2023)
Electron temperature fluctuation levels of the quasi-coherent mode across the plasma radius. EPJ Web of Conferences 2.
Zeitschriftenartikel
34, 101308 (2023)
Prospects of core-edge integrated no-ELM and small-ELM scenarios for future fusion devices. Nuclear Materials and Energy 3.
Zeitschriftenartikel
62, 026020 (2022)
Comparison of the influence of 2D and 3D geometry of the main chamber on plasma parameters in the SOL of ASDEX Upgrade. Nuclear Fusion 4.
Zeitschriftenartikel
129 (18), 165001 (2022)
Quasicontinuous Exhaust Scenario for a Fusion Reactor: The Renaissance of Small Edge Localized Modes. Physical Review Letters 5.
Zeitschriftenartikel
62, 042026 (2022)
Overview of JET results for optimising ITER operation. Nuclear Fusion 6.
Zeitschriftenartikel
62, 086004 (2022)
Developing a physics understanding of the quasi-continuous exhaust regime: pedestal profile and ballooning stability analysis. Nuclear Fusion 7.
Zeitschriftenartikel
33, 101303 (2022)
Experiments and modelling on ASDEX Upgrade and WEST in support of tool development for tokamak reactor armour melting assessments. Nuclear Materials and Energy 8.
Zeitschriftenartikel
62, 042018 (2022)
Overview of the TCV tokamak experimental programme. Nuclear Fusion 9.
Zeitschriftenartikel
62, 036004 (2022)
I-mode pedestal relaxation events in the Alcator C-Mod and ASDEX Upgrade tokamaks. Nuclear Fusion 10.
Zeitschriftenartikel
62, 042006 (2022)
Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario development. Nuclear Fusion 11.
Zeitschriftenartikel
26, 100879 (2021)
Infrared thermography in metallic environments of WEST and ASDEX Upgrade. Nuclear Materials and Energy 12.
Zeitschriftenartikel
26, 100890 (2021)
Broadening of the power fall-off length in a high density, high confinement H-mode regime in ASDEX Upgrade. Nuclear Materials and Energy 13.
Zeitschriftenartikel
63, 065012 (2021)
Real-time feedback system for divertor heat flux control at COMPASS tokamak. Plasma Physics and Controlled Fusion 14.
Zeitschriftenartikel
26, 100950 (2021)
Study of detachment in future ASDEX Upgrade alternative divertor configurations by means of EMC3-EIRENE. Nuclear Materials and Energy 15.
Zeitschriftenartikel
61, 024003 (2021)
H-mode scrape-off layer power width in the TCV tokamak. Nuclear Fusion 16.
Zeitschriftenartikel
62, 105014 (2020)
Role of electric currents for the SOL and divertor target heat fluxes in ASDEX Upgrade. Plasma Physics and Controlled Fusion 17.
Zeitschriftenartikel
60, 056016 (2020)
Turbulence driven widening of the near-SOL power width in ASDEX Upgrade H-Mode discharges. Nuclear Fusion 18.
Zeitschriftenartikel
62, 085004 (2020)
Correlation between near scrape-off layer power fall-off length and confinement properties in JET operated with carbon and ITER-like wall. Plasma Physics and Controlled Fusion 19.
Zeitschriftenartikel
25, 100854 (2020)
Continuous observation of filaments from the confined region to the far scrape-off layer. Nuclear Materials and Energy 20.
Zeitschriftenartikel
62, 105016 (2020)
Near- and far scrape-off layer transport studies in detached, small-ELM ASDEX Upgrade discharges by means of EMC3-EIRENE. Plasma Physics and Controlled Fusion