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Zeitschriftenartikel (64)
1.
Zeitschriftenartikel
48 (6), S. 1519 - 1524 (2020)
Transient Computational and Experimental Thermal Analysis of Graphite Foam Monoblock. IEEE Transactions on Plasma Science 2.
Zeitschriftenartikel
2020 (T171), 014003 (2020)
Assessment of the high heat flux performance of European DEMO divertor mock-ups. Physica Scripta 3.
Zeitschriftenartikel
2020 (T171), 014037 (2020)
Impact of H-mode plasma operation on pre-damaged tungsten divertor tiles in ASDEX Upgrade. Physica Scripta 4.
Zeitschriftenartikel
2020 (T171), 014015 (2020)
Application of tungsten–copper composite heat sink materials to plasma-facing component mock-ups. Physica Scripta 5.
Zeitschriftenartikel
157, 111610 (2020)
Performance assessment of thick W/Cu graded interlayer for DEMO divertor target. Fusion Engineering and Design 6.
Zeitschriftenartikel
20, 100688 (2019)
Manufacturing, high heat flux testing and post mortem analyses of a W-PIM mock-up. Nuclear Materials and Energy 7.
Zeitschriftenartikel
516, S. 178 - 184 (2019)
Synergistic effects of ELMs and H–He irradiation on the degradation behavior of tungsten treated with high-energy-rate forging. Journal of Nuclear Materials 8.
Zeitschriftenartikel
146, Pt. A, S. 216 - 219 (2019)
Progress in high heat flux testing of European DEMO divertor mock-ups. Fusion Engineering and Design 9.
Zeitschriftenartikel
59, 112004 (2019)
Overview of first Wendelstein 7-X high-performance operation. Nuclear Fusion 10.
Zeitschriftenartikel
59, 112014 (2019)
Overview of physics studies on ASDEX Upgrade. Nuclear Fusion 11.
Zeitschriftenartikel
146, Pt. A, S. 858 - 861 (2019)
Performance assessment of high heat flux W monoblock type target using thin graded and copper interlayers for application to DEMO divertor. Fusion Engineering and Design 12.
Zeitschriftenartikel
146, Pt. A, S. 417 - 420 (2019)
High heat-flux response of high-conductivity graphitic foam monoblocks. Fusion Engineering and Design 13.
Zeitschriftenartikel
46 (5), S. 1398 - 1401 (2018)
Design and Test of Wendelstein 7-X Water-Cooled Divertor Scraper. IEEE Transactions on Plasma Science 14.
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 15.
Zeitschriftenartikel
136, Pt. B, S. 1593 - 1596 (2018)
Manufacturing and testing of ITER-like divertor plasma facing mock-ups for DEMO. Fusion Engineering and Design 16.
Zeitschriftenartikel
16, S. 1 - 11 (2018)
European divertor target concepts for DEMO: Design rationales and high heat flux performance. Nuclear Materials and Energy 17.
Zeitschriftenartikel
T170, 014074 (2017)
Experimental results of near real-time protection system for plasma facing components in Wendelstein 7-X at GLADIS. Physica Scripta 18.
Zeitschriftenartikel
12, S. 575 - 581 (2017)
Surface modification of He pre-exposed tungsten samples by He plasma impact in the divertor manipulator of ASDEX Upgrade. Nuclear Materials and Energy 19.
Zeitschriftenartikel
T170, 014008 (2017)
Tungsten coating by ATC plasma spraying on CFC for WEST tokamak. Physica Scripta 20.
Zeitschriftenartikel
124, S. 207 - 210 (2017)
Overview of the different processes of tungsten coating implemented into WEST tokamak. Fusion Engineering and Design