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42 (3), S. 675 - 681 (2014)
Configuration Space Control Using the Example of In-vessel Components for Wendelstein 7-X. IEEE Transactions on Plasma Science 1243.
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89 (3), S. 146 - 154 (2014)
ASDEX Upgrade Discharge Control System – A real-time plasma control framework. Fusion Engineering and Design 1244.
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89 (5), S. 512 - 517 (2014)
Architectural Concept for the ITER Plasma Control System. Fusion Engineering and Design 1245.
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Monte Carlo simulation of initial breakdown phase for magnetised toroidal ICRF discharges. AIP Conference Proceedings 1246.
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1580, S. 239 - 242 (2014)
Effect of collisional heat transfer in ICRF power modulation experiment on ASDEX-Upgrade. AIP Conference Proceedings 1247.
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A multichannel reflectometer for the density profile measurements in front of the new ICRF antenna in ASDEX Upgrade. AIP Conference Proceedings 1248.
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Effect of the minority concentration on ion cyclotron resonance heating in presence of the ITER-like wall in JET. AIP Conference Proceedings 1249.
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Modulation of prompt fast-ion loss by applied n=2 fields in the DIII-D tokamak. Plasma Physics and Controlled Fusion 1250.
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Evidence for the neoclassical nature of the radial electric field in the edge transport barrier of ASDEX Upgrade. Nuclear Fusion 1251.
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Modelling of JET hybrid scenarios with GLF23 transport model: E×B shear stabilization of anomalous transport. Nuclear Fusion 1252.
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A simulation environment for ITER PCS development. Fusion Engineering and Design 1253.
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65 (3), S. 391 - 398 (2014)
Analysis of the Interlayer Joint Resistance of the Superconducting Coils of W7-X. Fusion Science and Technology 1254.
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DEMO divertor limitations during and in between ELMs. Nuclear Fusion 1255.
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Thermo-structural development of the ITER ICRF strap housing module. AIP Conference Proceedings 1256.
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42 (5), S. 1421 - 1424 (2014)
EBW Technology Applied on the ICRF Antenna Component. IEEE Transactions on Plasma Science 1257.
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LHCD and ICRF heating experiments in H-mode plasmas on EAST. AIP Conference Proceedings 1258.
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EAST ion cyclotron resonance heating system for long pulse operation. Fusion Engineering and Design 1259.
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L-mode radiative plasma edge studies for model validation in ASDEX Upgrade and JET. Journal of Nuclear Materials 1260.
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Science and technology research and development in support to ITER and the Broader Approach at CEA. Nuclear Fusion