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Zeitschriftenartikel (181)
141.
Zeitschriftenartikel
84 (2-6), S. 848 - 852 (2009)
Review of the high heat flux testing as an integrated part of W7-X divertor development. Fusion Engineering and Design 142.
Zeitschriftenartikel
T138, 014063 (4pp) (2009)
Automated jitter correction for IR image processing to assess the quality of W7-X high heat flux components. Physica Scripta 143.
Zeitschriftenartikel
T138, 014059 (4pp) (2009)
Experiences with tungsten coatings in high heat flux tests and under plasma load in ASDEX Upgrade. Physica Scripta 144.
Zeitschriftenartikel
390-391, S. 1118 - 1122 (2009)
Thermal response to heat fluxes of the W7-AS divertor surface submitted to surface modification under high temperature treatment. Journal of Nuclear Materials 145.
Zeitschriftenartikel
T138, 014031 (5pp) (2009)
Qualification of tungsten coatings on plasma-facing components for JET. Physica Scripta 146.
Zeitschriftenartikel
390-391, S. 934 - 937 (2009)
Development of divertor tungsten coatings for the JET ITER-like wall. Journal of Nuclear Materials 147.
Zeitschriftenartikel
T138, 014030 (4pp) (2009)
Current Status of the JET ITER-like Wall Project. Physica Scripta 148.
Zeitschriftenartikel
386-388, S. 856 - 859 (2009)
Examination of W7-X target elements after high heat flux testing. Journal of Nuclear Materials 149.
Zeitschriftenartikel
84 (7-11), S. 1317 - 1322 (2009)
Upgraded acceptance criteria from transient thermography control for the W7-X target elements. Fusion Engineering and Design 150.
Zeitschriftenartikel
84 (7-11), S. 1475 - 1478 (2009)
Progress in the design and development of a test divertor (TDU) for the start of W7-X operation. Fusion Engineering and Design 151.
Zeitschriftenartikel
84 (7-11), S. 1662 - 1665 (2009)
Industrial Scale 10 µm W Coating of CFC tiles for ITER-like Wall Project at JET. Fusion Engineering and Design 152.
Zeitschriftenartikel
49, 104009 (9pp) (2009)
Overview of ASDEX Upgrade results. Nuclear Fusion 153.
Zeitschriftenartikel
T128, S. 195 - 199 (2007)
Fabrication and testing of W7-X pre-series target elements. Physica Scripta 154.
Zeitschriftenartikel
82, S. 1634 - 1638 (2007)
Results of the examinations of the W7-X pre-series target elements. Fusion Engineering and Design 155.
Zeitschriftenartikel
T128, S. 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 156.
Zeitschriftenartikel
367-370, S. 1444 - 1448 (2007)
High Heat Flux Facility GLADIS - Operational Characteristics and Results of W7-X Pre-Series Target Tests. Journal of Nuclear Materials 157.
Zeitschriftenartikel
82, S. 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 158.
Zeitschriftenartikel
47, S. 222 - 227 (2007)
Tungsten and Beryllium Armour Development for the JET ITER-like Wall Project. Nuclear Fusion 159.
Zeitschriftenartikel
363-365, S. 1246 - 1250 (2007)
Tungsten Coatings for the JET ITER-like Wall Project. Journal of Nuclear Materials 160.
Zeitschriftenartikel
49, S. B59 - B70 (2007)
Plasma wall interaction and its implication in an all tungsten divertor tokamak. Invited Paper. Plasma Physics and Controlled Fusion