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49, 095002 (11pp) (2009)
Comparative Divertor-Transport Study for Helical Devices. Nuclear Fusion 1662.
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84 (2-6), pp. 788 - 792 (2009)
Recent developments at IPP on evaporation and control of caesium in negative ion sources. Fusion Engineering and Design 1663.
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84 (2-6), pp. 793 - 797 (2009)
Modified blanket cooling manifold system for ITER. Fusion Engineering and Design 1664.
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80, 053503 (9pp) (2009)
Scintillator Based Detector for MHD Induced Fast Ion Losses in the ASDEX Upgrade Tokamak. Review of Scientific Instruments 1665.
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49, 085014 (11pp) (2009)
MHD induced Fast-Ion Losses on ASDEX Upgrade. Nuclear Fusion 1666.
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84 (2-6), pp. 825 - 828 (2009)
Real time magnetic field and flux measurements for tokamak control using a multi-core PCI Express system. Fusion Engineering and Design 1667.
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49, 104010 (12pp) (2009)
Investigation of steady-state tokamak issues by long pulse experiments on Tore Supra. Nuclear Fusion 1668.
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49, 095021 (14pp) (2009)
Numerical simulations of fast ion loss measurements induced by magnetic islands in the ASDEX Upgrade tokamak. Nuclear Fusion 1669.
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386-388, pp. 772 - 775 (2009)
Cyclic heat load testing of improved CFC/Cu bonding for the W 7-X divertor targets. Journal of Nuclear Materials 1670.
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84 (2-6), pp. 848 - 852 (2009)
Review of the high heat flux testing as an integrated part of W7-X divertor development. Fusion Engineering and Design 1671.
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T138, 014063 (4pp) (2009)
Automated jitter correction for IR image processing to assess the quality of W7-X high heat flux components. Physica Scripta 1672.
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84 (2-6), pp. 170 - 177 (2009)
ASDEX Upgrade enhancements in view of ITER application. Invited Paper. Fusion Engineering and Design 1673.
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49, 115014 (9pp) (2009)
Compatibility of ITER scenarios with full tungsten wall in ASDEX Upgrade. Nuclear Fusion 1674.
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51, 045005 (14pp) (2009)
Negative Hydrogen Ion Transport in RF-driven Ion Sources for ITER NBI. Plasma Physics and Controlled Fusion 1675.
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49, 065012 (15pp) (2009)
Principal physics developments evaluated in the ITER design review. Nuclear Fusion 1676.
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84 (2-6), pp. 284 - 289 (2009)
Conceptual design of the ECH upper launcher system for ITER. Fusion Engineering and Design 1677.
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84 (2-6), pp. 915 - 922 (2009)
Design of the "half-size" ITER Neutral Beam Source for the Test Facility ELISE. Fusion Engineering and Design 1678.
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390-391, pp. 747 - 750 (2009)
Arcing in ASDEX Upgrade with a tungsten first wall. Journal of Nuclear Materials 1679.
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Experiences with tungsten coatings in high heat flux tests and under plasma load in ASDEX Upgrade. Physica Scripta 1680.
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Interfacial optimization of tungsten fibre-reinforced copper for high-temperature heat sink material for fusion application. Journal of Nuclear Materials