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Zeitschriftenartikel (59)
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1.ZeitschriftenartikelManufacturing, high heat flux testing and post mortem analyses of a W-PIM mock-up. Nuclear Materials and Energy 20 (2019)
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2.ZeitschriftenartikelSynergistic effects of ELMs and H–He irradiation on the degradation behavior of tungsten treated with high-energy-rate forging. Journal of Nuclear Materials 516, S. 178 - 184 (2019)
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3.ZeitschriftenartikelProgress in high heat flux testing of European DEMO divertor mock-ups. Fusion Engineering and Design 146, Pt. A, S. 216 - 219 (2019)
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4.ZeitschriftenartikelOverview of first Wendelstein 7-X high-performance operation. Nuclear Fusion 59, 112004 (2019)
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5.ZeitschriftenartikelOverview of physics studies on ASDEX Upgrade. Nuclear Fusion 59, 112014 (2019)
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6.ZeitschriftenartikelPerformance assessment of high heat flux W monoblock type target using thin graded and copper interlayers for application to DEMO divertor. Fusion Engineering and Design 146, Pt. A, S. 858 - 861 (2019)
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7.ZeitschriftenartikelHigh heat-flux response of high-conductivity graphitic foam monoblocks. Fusion Engineering and Design 146, Pt. A, S. 417 - 420 (2019)
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8.ZeitschriftenartikelDesign and Test of Wendelstein 7-X Water-Cooled Divertor Scraper. IEEE Transactions on Plasma Science 46 (5), S. 1398 - 1401 (2018)
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9.ZeitschriftenartikelThermal analysis and high heat flux testing of unidirectional carbon–carbon composite for infrared imaging diagnostic. Journal of Thermal Analysis and Calorimetry 134 (1), S. 143 - 155 (2018)
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10.ZeitschriftenartikelManufacturing and testing of ITER-like divertor plasma facing mock-ups for DEMO. Fusion Engineering and Design 136, Pt. B, S. 1593 - 1596 (2018)
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11.ZeitschriftenartikelEuropean divertor target concepts for DEMO: Design rationales and high heat flux performance. Nuclear Materials and Energy 16 (2018)
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12.ZeitschriftenartikelExperimental results of near real-time protection system for plasma facing components in Wendelstein 7-X at GLADIS. Physica Scripta T170, 014074 (2017)
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13.ZeitschriftenartikelSurface modification of He pre-exposed tungsten samples by He plasma impact in the divertor manipulator of ASDEX Upgrade. Nuclear Materials and Energy 12 (2017)
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14.ZeitschriftenartikelTungsten coating by ATC plasma spraying on CFC for WEST tokamak. Physica Scripta T170, 014008 (2017)
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15.ZeitschriftenartikelOverview of the different processes of tungsten coating implemented into WEST tokamak. Fusion Engineering and Design 124, S. 207 - 210 (2017)
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16.ZeitschriftenartikelHigh heat flux testing of mm thick tungsten coatings on carbon-fiber composites for the JT-60SA tokamak. Physica Scripta T170, 014029 (2017)
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17.ZeitschriftenartikelResults of high heat flux qualification tests of W monoblock components for WEST. Physica Scripta T170, 014001 (2017)
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18.ZeitschriftenartikelPotential approach of IR-analysis for high heat flux quality assessment of divertor tungsten monoblock components. Fusion Engineering and Design 124, S. 202 - 206 (2017)
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19.ZeitschriftenartikelIrradiation effects of hydrogen and helium plasma on different grade tungsten materials. Nuclear Materials and Energy 12 (2017)
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20.ZeitschriftenartikelRealization of high heat flux tungsten monoblock type target with graded interlayer for application to DEMO divertor. Physica Scripta T170, 014022 (2017)