Journal Article (342)
81.
Journal Article
47, pp. 264 - 270 (2007)
Progress of the Development of the IPP RF Negative Ion Source for the ITER Neutral Beam System. Nuclear Fusion 82.
Journal Article
82, pp. 407 - 423 (2007)
RADI - a RF source size-scaling experiment towards the ITER neutral beam negative ion source. Fusion Engineering and Design 83.
Journal Article
82, pp. 887 - 896 (2007)
Technical overview and first results of the half-size ITER NNBI source. Fusion Engineering and Design 84.
Journal Article
47, pp. S718 - S726 (2007)
Experimental progress on zonal flow physics in toroidal plasmas. Nuclear Fusion 85.
Journal Article
82, pp. 1391 - 1395 (2007)
Final test of the W7-X control coils power supply and its integration into the overall control environment. Fusion Engineering and Design 86.
Journal Article
82, pp. 912 - 919 (2007)
Studies on the radio frequency power supply system for the ITER NB injector ion source. Fusion Engineering and Design 87.
Journal Article
47, pp. L10 - L15 (2007)
NTM induced fast ion losses in ASDEX Upgrade. Nuclear Fusion 88.
Journal Article
82, pp. 1591 - 1598 (2007)
Structural evaluation of the busbar system of Wendelstein 7-X stellarator. Fusion Engineering and Design 89.
Journal Article
40, pp. 2203 - 2218 (2007)
A study of a simple gyrotron equation. Journal of Physics A: Mathematical and Theoretical 90.
Journal Article
363-365, pp. 893 - 897 (2007)
Deuterium retention in rhenium-doped tungsten. Journal of Nuclear Materials 91.
Journal Article
Chapter 6: Steady state operation. Progress in the ITER Physics Basis, pp. S285 - S336 (2007)
92.
Journal Article
49, pp. B173 - B182 (2007)
Global full-f gyrokinetic simulations of plasma turbulence. Invited Paper. Plasma Physics and Controlled Fusion 93.
Journal Article
47 (9), pp. L26 - L29 (2007)
Density Profile Peaking in Low Collisionality H-modes: Comparison of Alcator C-mod Data to ASDEX Upgrade/JET Scalings. Nuclear Fusion 94.
Journal Article
T128, pp. 218 - 221 (2007)
Power load limits of the WENDELSTEIN 7-X target elements - comparison of experimental results and design values for power loads up to the critical heat flux. Physica Scripta 95.
Journal Article
367-370, pp. 1444 - 1448 (2007)
High Heat Flux Facility GLADIS - Operational Characteristics and Results of W7-X Pre-Series Target Tests. Journal of Nuclear Materials 96.
Journal Article
82, pp. 1713 - 1719 (2007)
High heat flux tests of the WENDELSTEIN 7-X pre-series target elements - Experimental evaluation of the thermo-mechanical behaviour. Fusion Engineering and Design 97.
Journal Article
Chapter 8: Plasma operation and control. Progress in the ITER Physics Basis, pp. S385 - S403 (2007)
98.
Journal Article
82, pp. 2390 - 2398 (2007)
Treatment of ITER plasma facing components: Current status and remaining open issues before ITER implementation. Fusion Engineering and Design 99.
Journal Article
47, pp. S622 - S634 (2007)
Overview of ASDEX Upgrade Results. Nuclear Fusion 100.
Journal Article
47 (3), pp. 183 - 189 (2007)
Plasma profiles in a cylindrical helicon discharge with converging magnetic source field. Contributions to Plasma Physics