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Mitigation of divertor edge localised mode power loading by impurity seeding. Nuclear Fusion 103.
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Investigation of ELM-related Larmor ion flux into toroidal gaps of divertor target plates. Nuclear Fusion 104.
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Wall conditioning effects and boron migration during boron powder injection in ASDEX Upgrade. Nuclear Materials and Energy 105.
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Admixed pellets for fast and efficient delivery of plasma enhancement gases: Investigations at AUG exploring the option for EU-DEMO. Fusion Engineering and Design 106.
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Gyro orbit simulations of neutral beam injection in Wendelstein 7-X. Nuclear Fusion 107.
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Fundamental ICRF Heating of Deuterium Ions in JET-DTE2. AIP Conference Proceedings 108.
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Turbulence characterization during the suppression of edge-localized modes by magnetic perturbations on ASDEX Upgrade. Nuclear Fusion 109.
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Effect of triangularity on plasma turbulence and the SOL-width scaling in L-mode diverted tokamak configurations. Plasma Physics and Controlled Fusion 110.
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Annihilation-gamma-based diagnostic techniques for magnetically confined electron-positron pair plasma. Journal of Plasma Physics 111.
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Parameter dependencies of the separatrix density in low triangularity L-mode and H-mode JET-ILW plasmas. Nuclear Fusion 112.
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ICRF heating schemes for the HL-2M tokamak. Nuclear Fusion 113.
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Validation of IMEP on Alcator C-Mod and JET-ILW ELMy H-mode plasmas. Plasma Physics and Controlled Fusion 114.
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Tungsten accumulation during ion cyclotron resonance heating operation on WEST. Plasma Physics and Controlled Fusion 115.
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Development of a MMC demonstrator for nuclear fusion devices power supplies. Fusion Engineering and Design 116.
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Experiments in high-performance JET plasmas in preparation of second harmonic ICRF heating of tritium in ITER. Nuclear Fusion 117.
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Kinetic study of the bifurcation of resonant magnetic perturbations for edge localized mode suppression in ASDEX Upgrade. Nuclear Fusion 118.
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JET D-T scenario with optimized non-thermal fusion. Nuclear Fusion 119.
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Studies on EU-DEMO 3D coils requirements and conceptual design for error field correction and plasma control. Fusion Engineering and Design 120.
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Recent Analysis of the ITER Ion Cyclotron Antenna with the TOPICA Code. AIP Conference Proceedings