Publikationen von H. Greuner
Alle Typen
Zeitschriftenartikel (196)
61.
Zeitschriftenartikel
: Design and Test of Wendelstein 7-X Water-Cooled Divertor Scraper. IEEE Transactions on Plasma Science 46 (5), S. 1398 - 1401 (2018)
62.
Zeitschriftenartikel
136, Pt. A, S. 558 - 562 (2018)
FEM and thermal fatigue testing comparison of ITER-like divertor PFUs mock-ups for DEMO. Fusion Engineering and Design 63.
Zeitschriftenartikel
134 (1), S. 143 - 155 (2018)
Thermal analysis and high heat flux testing of unidirectional carbon–carbon composite for infrared imaging diagnostic. Journal of Thermal Analysis and Calorimetry 64.
Zeitschriftenartikel
: Results on the use of tungsten heavy alloys in the divertor of ASDEX Upgrade. Journal of Nuclear Materials 511, S. 567 - 573 (2018)
65.
Zeitschriftenartikel
: Manufacturing and testing of ITER-like divertor plasma facing mock-ups for DEMO. Fusion Engineering and Design 136, Pt. B, S. 1593 - 1596 (2018)
66.
Zeitschriftenartikel
58, 096001 (2018)
Surface modification of W–V alloy exposed to high heat flux helium neutral beams. Nuclear Fusion 67.
Zeitschriftenartikel
: European divertor target concepts for DEMO: Design rationales and high heat flux performance. Nuclear Materials and Energy 16, S. 1 - 11 (2018)
68.
Zeitschriftenartikel
: Cracks avoidance with a modified solid tungsten divertor in ASDEX Upgrade. Fusion Engineering and Design 136, Pt. B, S. 1052 - 1057 (2018)
69.
Zeitschriftenartikel
T170, 014074 (2017)
Experimental results of near real-time protection system for plasma facing components in Wendelstein 7-X at GLADIS. Physica Scripta 70.
Zeitschriftenartikel
13, S. 74 - 80 (2017)
Microstructural stability of spark-plasma-sintered Wf/W composite with zirconia interface coating under high-heat-flux hydrogen beam irradiation. Nuclear Materials and Energy 71.
Zeitschriftenartikel
124, S. 348 - 351 (2017)
Summary of the production of the divertor target elements of Wendelstein 7-X. Fusion Engineering and Design 72.
Zeitschriftenartikel
: Plasma-wall interaction studies within the EUROfusion consortium: progress on plasma-facing components development and qualification. Nuclear Fusion 57, 116041 (2017)
73.
Zeitschriftenartikel
: Surface modification of He pre-exposed tungsten samples by He plasma impact in the divertor manipulator of ASDEX Upgrade. Nuclear Materials and Energy 12, S. 575 - 581 (2017)
74.
Zeitschriftenartikel
121, S. 211 - 217 (2017)
Thermal-hydraulics modeling for prototype testing of the W7-X high heat flux scraper element. Fusion Engineering and Design 75.
Zeitschriftenartikel
124, S. 432 - 436 (2017)
ITER-like divertor target for DEMO: Design study and fabrication test. Fusion Engineering and Design 76.
Zeitschriftenartikel
T170, 014008 (2017)
Tungsten coating by ATC plasma spraying on CFC for WEST tokamak. Physica Scripta 77.
Zeitschriftenartikel
: Overview of the different processes of tungsten coating implemented into WEST tokamak. Fusion Engineering and Design 124, S. 207 - 210 (2017)
78.
Zeitschriftenartikel
: High heat flux testing of mm thick tungsten coatings on carbon-fiber composites for the JT-60SA tokamak. Physica Scripta T170, 014029 (2017)
79.
Zeitschriftenartikel
: The development and testing of the thermal break divertor monoblock target design delivering 20 MW m-2 heat load capability. Physica Scripta T170, 014042 (2017)
80.
Zeitschriftenartikel
T170, 014001 (2017)
Results of high heat flux qualification tests of W monoblock components for WEST. Physica Scripta