Publikationen des Bereichs Tokamak-Szenario-Entwicklung
Zeitschriftenartikel (186)
1.
Zeitschriftenartikel
X-mode raw data analysis of the new AUG ICRF antenna edge density profile reflectometer. Fusion Engineering and Design 123, S. 816 - 819 (2017)
2.
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Gyrokinetic study of turbulent convection of heavy impurities in tokamak plasmas at comparable ion and electron heat fluxes. Nuclear Fusion 57, 022009 (2017)
3.
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Density gradient driven microinstabilities and turbulence in ASDEX Upgrade pellet fuelled plasmas. Nuclear Fusion 57, 116053 (2017)
4.
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A comparison of the impact of central ECRH and central ICRH on the tungsten behaviour in ASDEX Upgrade H-mode plasmas. Nuclear Fusion 57, 056015 (2017)
5.
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The DC-link of the inverter system BUSSARD for ASDEX Upgrade invessel saddle coils. Fusion Engineering and Design 124, S. 40 - 44 (2017)
6.
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Kinetic simulations of X-B and O-X-B mode conversion and its deterioration at high input power. Nuclear Fusion 57, 116024 (2017)
7.
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Status of the development of diagnostic pressure gauges for the operation in ITER. Fusion Engineering and Design 123, S. 1049 - 1053 (2017)
8.
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Integrating a distributed antenna in DEMO: Requirements and challenges. Fusion Engineering and Design 123, S. 431 - 434 (2017)
9.
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Technical rehearsal of tritium operation at JET. Fusion Engineering and Design 123, S. 196 - 200 (2017)
10.
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Power exhaust by SOL and pedestal radiation at ASDEX Upgrade and JET. Nuclear Materials and Energy 12, S. 111 - 118 (2017)
11.
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Systems code studies on the optimization of design parameters for a pulsed DEMO tokamak reactor. Fusion Engineering and Design 123, S. 206 - 211 (2017)
12.
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Comment on 'On the fusion triple product and fusion power gain of tokamak pilot plants and reactors', by A. Costley. Nuclear Fusion 57, 038001 (2017)
13.
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Direct toroidal torque driven by ICRF heating and its dependence on the plasma rotation. Nuclear Fusion 57, 076017 (2017)
14.
Zeitschriftenartikel
Progress in reducing ICRF-specific impurity release in ASDEX upgrade and JET. Nuclear Materials and Energy 12, S. 1194 - 1198 (2017)
15.
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Making ICRF power compatible with a high-Z wall in ASDEX Upgrade. Plasma Physics and Controlled Fusion 59, 014022 (2017)
16.
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Characterization of 3-strap antennas in ASDEX Upgrade. EPJ Web of Conferences 157, 03005 (2017)
17.
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Non-inductive improved H-mode operation at ASDEX Upgrade. Nuclear Fusion 57, 126041 (2017)
18.
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An analytical expression for ion velocities at the wall including the sheath electric field and surface biasing for erosion modeling at JET ILW. Nuclear Materials and Energy 12, S. 341 - 345 (2017)
19.
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Summary of the production of the divertor target elements of Wendelstein 7-X. Fusion Engineering and Design 124, S. 348 - 351 (2017)
20.
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Plasma-wall interaction studies within the EUROfusion consortium: progress on plasma-facing components development and qualification. Nuclear Fusion 57, 116041 (2017)