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Theory of a cylindrical Langmuir probe parallel to the magnetic field and its calibration with interferometry. Review of Scientific Instruments 742.
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60, 085013 (2018)
Density control by pellets in plasmas with ELM mitigation by RMPs in the ASDEX Upgrade tokamak. Plasma Physics and Controlled Fusion 743.
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60, 045002 (2018)
Effects of density gradients and fluctuations at the plasma edge on ECEI measurements at ASDEX Upgrade. Plasma Physics and Controlled Fusion 744.
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58, 112011 (2018)
Characterization of low-frequency inter-ELM modes of H-mode discharges at ASDEX Upgrade. Nuclear Fusion 745.
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136, Pt. B, pp. 1035 - 1139 (2018)
Effect of neutral leaks on pumping efficiency in 3D DEMO divertor configuration. Fusion Engineering and Design 746.
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58, 026031 (2018)
Ion heat transport dynamics during edge localized mode cycles at ASDEX Upgrade. Nuclear Fusion 747.
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58, 026019 (2018)
Multi-machine analysis of termination scenarios with comparison to simulations of controlled shutdown of ITER discharges. Nuclear Fusion 748.
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187, 01023 (2018)
Prediction of ohmic losses in miter bend polarizers. EPJ Web of Conferences 749.
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46 (5), pp. 1576 - 1579 (2018)
Thermal and Mechanical Analysis of the Wendelstein 7-X Cryo-Vacuum Pump Plug-In. IEEE Transactions on Plasma Science 750.
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58, 082032 (2018)
RABBIT: Real-time simulation of the NBI fast-ion distribution. Nuclear Fusion 751.
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Gyrokinetic study of slowing-down α particles transport due to trapped electron mode turbulence. Physics of Plasmas 752.
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136, Pt. B, pp. 1052 - 1057 (2018)
Cracks avoidance with a modified solid tungsten divertor in ASDEX Upgrade. Fusion Engineering and Design 753.
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58, 126005 (2018)
EMC3-EIRENE modeling of edge plasma to improve the ICRF coupling with local gas puffing in DEMO. Nuclear Fusion 754.
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123, pp. 816 - 819 (2017)
X-mode raw data analysis of the new AUG ICRF antenna edge density profile reflectometer. Fusion Engineering and Design 755.
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57, 022009 (2017)
Gyrokinetic study of turbulent convection of heavy impurities in tokamak plasmas at comparable ion and electron heat fluxes. Nuclear Fusion 756.
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57, 116053 (2017)
Density gradient driven microinstabilities and turbulence in ASDEX Upgrade pellet fuelled plasmas. Nuclear Fusion 757.
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57, 056015 (2017)
A comparison of the impact of central ECRH and central ICRH on the tungsten behaviour in ASDEX Upgrade H-mode plasmas. Nuclear Fusion 758.
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The DC-link of the inverter system BUSSARD for ASDEX Upgrade invessel saddle coils. Fusion Engineering and Design 759.
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Kinetic simulations of X-B and O-X-B mode conversion and its deterioration at high input power. Nuclear Fusion 760.
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Status of the development of diagnostic pressure gauges for the operation in ITER. Fusion Engineering and Design