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Overview of toroidal momentum transport. Nuclear Fusion 1522.
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Numerical simulation of fast ion loss detector measurements for fishbones on JET. Nuclear Fusion 1523.
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Comparison of different pellet injection systems for ELM pacing. Fusion Engineering and Design 1524.
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W7-X neutral-beam-injection: Selection of the NBI source positions for experiment start-up. Fusion Engineering and Design, Special Issue 1525.
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Simultaneous analysis of ion and electron heat transport by power modulation in JET. Nuclear Fusion 1526.
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Density pump-out compensation during type-I edge localized mode control experiments with n = 1 perturbation fields on JET. Plasma Physics and Controlled Fusion 1527.
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COTS-Based High-Data-Throughput Acquisition System for a Real-Time Reflectometry Diagnostic. IEEE Transactions on Nuclear Science 1528.
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ELM characteristics and divertor loads in ASDEX Upgrade helium discharges. Supplement, pp. S877 - S880 (2011)
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Confinement of 'improved H-modes' in the all-tungsten ASDEX Upgrade with nitrogen seeding. Nuclear Fusion 1531.
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Local effects of ECRH on argon transport in L-mode discharges at ASDEX Upgrade. Plasma Physics and Controlled Fusion 1532.
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Development of a thermo-hydraulic bypass leakage test method for the Wendelstein 7-X target element cooling structure. Fusion Engineering and Design 1533.
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Characterization and interpretation of the Edge Snake in between type-I edge localized modes at ASDEX Upgrade. Plasma Physics and Controlled Fusion 1534.
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Design, manufacture and testing of the glow discharge electrodes for Wendelstein 7-X. Fusion Engineering and Design 1535.
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ECRH-assisted plasma start-up with toroidally inclined launch: multi-machine comparison and perspectives for ITER. Nuclear Fusion 1536.
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Studies of edge localized mode mitigation with new active in-vessel saddle coils in ASDEX Upgrade. Plasma Physics and Controlled Fusion 1537.
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First observation of edge localized modes mitigation with resonant and nonresonant magnetic perturbations in ASDEX Upgrade. Physical Review Letters 1538.
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Experimental investigation and validation of neutral beam current drive for ITER through ITPA Joint Experiments. Nuclear Fusion 1539.
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Power load characterization for type-I ELMy H-modes in JET. Nuclear Fusion 1540.
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Integrated operation of diagnostics and control. Fusion Engineering and Design