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Development of a Scalable MMC Pulsed Power Supply through HIL Methodology. Energies 162.
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Varistor development for in-vessel magnetic field coils in nuclear fusion devices. Fusion Engineering and Design 163.
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2984 (1), 030006 (2023)
Filaments as the Origin of HHFW Losses in NSTX. AIP Conference Proceedings 164.
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Resonance cones in cold plasma: Origin, singularities, and power flow. Physics of Plasmas 165.
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Experimental validation of the intensity refractometry principle for density measurements at the edge of a tokamak. Fusion Engineering and Design 166.
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65, 095011 (2023)
Impact of toroidal rotation on the resistive ballooning modes in ASDEX Upgrade tokamak. Plasma Physics and Controlled Fusion 167.
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Electron temperature fluctuation levels of the quasi-coherent mode across the plasma radius. EPJ Web of Conferences 168.
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Prospects of core-edge integrated no-ELM and small-ELM scenarios for future fusion devices. Nuclear Materials and Energy 169.
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71 (6), pp. 2558 - 2566 (2023)
Single-and Two-Frequency Sub-THz Waveguide Notch Filters with Rejection Frequencies within and beyond the Passband. IEEE Transactions on Microwave Theory and Techniques 170.
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63, 066018 (2023)
Characterisation of electron cyclotron wall conditioning plasma in ASDEX Upgrade. Nuclear Fusion 171.
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Real-time implementation of the high-fidelity NBI code RABBIT into the discharge control system of ASDEX Upgrade. Nuclear Fusion 172.
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Parametric study of midplane gas puffing to maximize ICRF power coupling in ITER. Nuclear Fusion 173.
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65, 035008 (2023)
Drift kinetic effects on plasma response to resonant magnetic perturbation for EU DEMO design. Plasma Physics and Controlled Fusion 174.
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Comparison of momentum transport in matched hydrogen and deuterium H-mode plasmas in ASDEX Upgrade. Nuclear Fusion 175.
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Experimental determination of the three components of toroidal momentum transport in the core of a tokamak plasma. Nuclear Fusion 176.
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Investigation of helium exhaust dynamics at the ASDEX Upgrade tokamak with full-tungsten wall. Nuclear Fusion 177.
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Confinement properties of L-mode plasmas in ASDEX Upgrade and full-radius predictions of the TGLF transport model. Nuclear Fusion 178.
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Containment structures and port configurations. Fusion Engineering and Design 179.
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Confinement in electron heated plasmas in Wendelstein 7-X and ASDEX Upgrade; the necessity to control turbulent transport. Nuclear Fusion 180.
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Development of a concept and basis for the DEMO diagnostic and control system. Fusion Engineering and Design