Publikationen 2019

Beiträge in referierten Zeitschriften 2019

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Simulation of magnetic control of the plasma shape on the DEMO tokamak
Fusion engineering and design 146(Part A), 728 - 731 () [10.1016/j.fusengdes.2019.01.065] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Tritium retention in W plasma-facing materials: Impact of the material structure and helium irradiation
Nuclear materials and energy 19, 403 - 410 () [10.1016/j.nme.2019.03.005] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Diagnostics for plasma control – From ITER to DEMO
Fusion engineering and design 146(Part A), 465 - 472 () [10.1016/j.fusengdes.2018.12.092] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Improved ERO modelling of beryllium erosion at ITER upper first wall panel using JET-ILW and PISCES-B experience
Nuclear materials and energy 19, 510 - 515 () [10.1016/j.nme.2019.03.016] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Chemically assisted physical sputtering of Tungsten: Identification via the 6 Π → 6 Σ + transition of WD in TEXTOR and ASDEX Upgrade plasmas
Nuclear materials and energy 18, 50 - 55 () [10.1016/j.nme.2018.12.004] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Erosion, screening, and migration of tungsten in the JET divertor
Nuclear fusion 59(9), 096035 - () [10.1088/1741-4326/ab2aef] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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A new multi-channel Mach probe measuring the radial ion flow velocity profile in the boundary plasma of the W7-X stellarator
Review of scientific instruments 90(3), 033502 - () [10.1063/1.5054279] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Pre-conceptual study of the European DEMO neutron diagnostics
Journal of Instrumentation 14(09), C09001 - C09001 () [10.1088/1748-0221/14/09/C09001] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Materials development for new high heat-flux component mock-ups for DEMO
Fusion engineering and design 146, 1431 - 1436 () [10.1016/j.fusengdes.2019.02.098] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Erosion and deposition investigations on Wendelstein 7-X first wall components for the first operation phase in divertor configuration
Fusion engineering and design 146(Part A), 242 - 245 () [10.1016/j.fusengdes.2018.12.031] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Measurement of the Magnetic Field in a Linear Magnetized Plasma by Tunable Diode Laser Absorption Spectroscopy
Atoms 7(2), 48 - () [10.3390/atoms7020048] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Polarization by light reflection at metallic surfaces observed in the shape of the Balmer- α line of low density plasmas
Physics of plasmas 26(7), 073513 - () [10.1063/1.5088931] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Operation of probe heads on the Multi-Purpose-Manipulator at W7-X in OP 1.2a
Fusion engineering and design 146, 2353 - 2355 () [10.1016/j.fusengdes.2019.03.188] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Investigation of 3D effects on heat fluxes in performance-optimized island divertor configurations at Wendelstein 7-X
Nuclear materials and energy 18, 262 - 267 () [10.1016/j.nme.2019.01.006] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Investigation of hydrogen isotope retention mechanisms in beryllium: High resolution TPD measurements
Nuclear materials and energy 19, 440 - 444 () [10.1016/j.nme.2019.03.018] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Surface roughness effect on Mo physical sputtering and re-deposition in the linear plasma device PSI-2 predicted by ERO2.0
Nuclear materials and energy 19, 13 - 18 () [10.1016/j.nme.2019.02.006] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Plastic deformation of tungsten due to deuterium plasma exposure: Insights from micro-compression tests
Scripta materialia 162, 132 - 135 () [10.1016/j.scriptamat.2018.10.052] BibTeX | EndNote: XML, Text | RIS

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Overview of the DEMO staged design approach in Europe
Nuclear fusion 59(6), 066013 - () [10.1088/1741-4326/ab1178] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Methods for quantitative study of divertor heat loads on W7-X
Nuclear fusion 59(6), 066007 - () [10.1088/1741-4326/ab0f49] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Effects of toroidal plasma current on divertor power depositions on Wendelstein 7-X
Nuclear fusion 59(10), 106015 - () [10.1088/1741-4326/ab32c2] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Conceptual studies on spectroscopy and radiation diagnostic systems for plasma control on DEMO
Fusion engineering and design 146, 2297 - 2301 () [10.1016/j.fusengdes.2019.03.176] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Development of glow discharge and electron cyclotron resonance heating conditioning on W7-X
Nuclear materials and energy 18, 227 - 232 () [10.1016/j.nme.2018.12.010] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Influence of thermal shocks on the He induced surface morphology on tungsten
Nuclear materials and energy 18, 321 - 325 () [10.1016/j.nme.2019.01.029] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Modelling of the effect of ELMs on fuel retention at the bulk W divertor of JET
Nuclear materials and energy 19, 397 - 402 () [10.1016/j.nme.2019.03.013] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Impact of Surface Roughness on Ion-Surface Interactions Studied with Energetic Carbon Ions 13C+ on Tungsten Surfaces
Condensed Matter 4(1), 29 - () [10.3390/condmat4010029] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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An assessment of nitrogen concentrations from spectroscopic measurements in the JET and ASDEX upgrade divertor
Nuclear materials and energy 18, 147 - 152 () [10.1016/j.nme.2018.12.012] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Atmospheric plasma spraying of functionally graded steel/tungsten layers for the first wall of future fusion reactors
Surface and coatings technology 366, 170 - 178 () [10.1016/j.surfcoat.2019.03.017] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Ultra-fast sintered functionally graded Fe/W composites for the first wall of future fusion reactors
Composites / B Engineering Part B 164, 205 - 214 () [10.1016/j.compositesb.2018.11.078] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Comparison of the hydrogen permeation through fusion relevant steels and the influence of oxidized and rough surfaces
Nuclear materials and energy 19, 55 - 58 () [10.1016/j.nme.2019.01.030] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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The software and hardware architecture of the real-time protection of in-vessel components in JET-ILW
Nuclear fusion 59(7), 076016 - () [10.1088/1741-4326/ab1a79]  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

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Determination of tungsten sources in the JET-ILW divertor by spectroscopic imaging in the presence of a strong plasma continuum
Nuclear materials and energy 18, 118 - 124 () [10.1016/j.nme.2018.12.009] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Detailed structural analysis of a graded TF coil winding pack for EU DEMO
Fusion engineering and design 146, 535 - 538 () [10.1016/j.fusengdes.2019.01.016]  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

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An upgraded LIBS system on linear plasma device PSI-2 for in situ diagnostics of plasma-facing materials
Fusion engineering and design 146(Part A), 96 - 99 () [10.1016/j.fusengdes.2018.11.044] BibTeX | EndNote: XML, Text | RIS

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Simulations of the effects of pre-seeded magnetic islands on the generation of runaway current during disruption on J-TEXT
Physics of plasmas 26(6), 062508 - () [10.1063/1.5100093] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Modelling of tungsten erosion and deposition in the divertor of JET-ILW in comparison to experimental findings
Nuclear materials and energy 18, 239 - 244 () [10.1016/j.nme.2019.01.004] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Sublimation of advanced tungsten alloys under DEMO relevant accidental conditions
Fusion engineering and design 146(Part A), 1198-1202 () [10.1016/j.fusengdes.2019.02.039]  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

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Overview of first Wendelstein 7-X high-performance operation
Nuclear fusion 59(11), 112004 - () [10.1088/1741-4326/ab03a7] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Plug flow reactor model of the plasma chemical conversion of CO2
Plasma sources science and technology 28(9), 095002 () [10.1088/1361-6595/ab3774] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Investigation of turbulence rotation and radial electric field in the island divertor and plasma edge at W7-X
Plasma physics and controlled fusion 61(5), 054003 - () [10.1088/1361-6587/ab0624]  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

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Influence of plasma impurities on the fuel retention in tungsten
Nuclear fusion 59(8), 086029 - () [10.1088/1741-4326/ab235d]  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

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Design status of the ITER core CXRS diagnostic setup
Fusion engineering and design 146(Part A), 228 - 231 () [10.1016/j.fusengdes.2018.12.026]  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

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Micro- and macro- elastic properties of tungsten fiber-reinforced tungsten composites probed by nano-indentation and laser ultrasonics
Nuclear materials and energy 19, 262 - 266 () [10.1016/j.nme.2019.03.001] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Measurement of the edge ion temperature in W7-X with island divertor by a retarding field analyzer probe
Nuclear fusion 59(12), 126002 - () [10.1088/1741-4326/ab3a79] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Overview of the recent experimental research on the J-TEXT tokamak
Nuclear fusion 59(11), 112016 - () [10.1088/1741-4326/ab1a72] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Optimization of single crystal mirrors for ITER diagnostics
Fusion engineering and design 146, 1450 - 1453 () [10.1016/j.fusengdes.2019.02.102] BibTeX | EndNote: XML, Text | RIS

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The effects of magnetic topology on the scrape-off layer turbulence transport in the first divertor plasma operation of Wendelstein 7-X using a new combined probe
Nuclear fusion 59(6), 066001 - () [10.1088/1741-4326/ab0d29]  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

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High Pulse Numbe Thermal Shock Testing of Tungsten Alloys Produced by Powder Injection Molding
Nuclear materials and energy 20, 100680 () [10.1016/j.nme.2019.100680] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Implications of uncertainties on European DEMO design
Nuclear fusion 59(6), 066012 - () [10.1088/1741-4326/ab13e2] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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On the nature of carbon embrittlement of tungsten fibers during powder metallurgical processes
Fusion engineering and design 145, 18 - 22 () [10.1016/j.fusengdes.2019.05.033] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Fracture behavior of random distributed short tungsten fiber-reinforced tungsten composites
Nuclear fusion 59(8), 086034 - () [10.1088/1741-4326/ab25b0] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Emission of Fast Hydrogen Atoms in a Low Density Gas Discharge—The Most “Natural” Mirror Laboratory
Atoms 7(3), 81 - () [10.3390/atoms7030081] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Modeling of H/D isotope-exchange in crystalline beryllium
Nuclear materials and energy 20, 100682 - () [10.1016/j.nme.2019.100682] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Bolometer developments in diagnostics for magnetic confinement fusion
Journal of Instrumentation 14(10), C10004 - C10004 () [10.1088/1748-0221/14/10/C10004] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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The Core-Plasma CXRS Diagnostic for ITER: An Introduction to the Current Design
Journal of fusion energy 38(3-4), 264-282 () [10.1007/s10894-018-0202-1]  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

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On the use of rhodium mirrors for optical diagnostics in ITER
Fusion engineering and design 146(B), 2514-2518 () [10.1016/j.fusengdes.2019.04.031]  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

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Endoscopes for observation of plasma-wall interactions in the divertor of Wendelstein 7-X
Fusion engineering and design 146, 19 - 22 () [10.1016/j.fusengdes.2018.11.009] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Influence of heavier impurity deposition on surface morphology development and sputtering behavior explored in multiple linear plasma devices
Nuclear materials and energy 18, 67 - 71 () [10.1016/j.nme.2018.12.008] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Depth resolved analysis of hydrogen in W7-X graphite components using laser-induced ablation-quadrupole mass spectrometry (LIA-QMS)
Nuclear materials and energy 18, 153 - 158 () [10.1016/j.nme.2018.12.019] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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First results from divertor operation in Wendelstein 7-X
Plasma physics and controlled fusion 61(1), 014035 - () [10.1088/1361-6587/aaec25] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Long-lived coupled peeling ballooning modes preceding ELMs on JET
Nuclear fusion 59(5), 056004 - () [10.1088/1741-4326/ab0031]  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

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European materials development: Results and perspective
Fusion engineering and design 146, 1300 - 1307 () [10.1016/j.fusengdes.2019.02.063] BibTeX | EndNote: XML, Text | RIS

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Diffusion model of the impact of helium and argon impurities on deuterium retention in tungsten
Nuclear fusion 59(4), 046004 - () [10.1088/1741-4326/aafe8d]  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

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On the possibility of track length based Monte-Carlo algorithms for stationary drift-diffusion systems with sources and sinks
Journal of computational physics 377, 219 - 231 () [10.1016/j.jcp.2018.07.051] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Model discovery for studies of surface morphological modifications based on Kuramoto-Sivashinsky dynamics
Physical review / E 100(3), 033312 () [10.1103/PhysRevE.100.033312] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Beryllium global erosion and deposition at JET-ILW simulated with ERO2.0
Nuclear materials and energy 18, 331 - 338 () [10.1016/j.nme.2019.01.015] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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First Monte-Carlo modelling of global beryllium migration in ITER using ERO2.0
Contributions to plasma physics 60(5-6), e201900149 - () [10.1002/ctpp.201900149] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Preferential sputtering induced Cr-Diffusion during plasma exposure of WCrY smart alloys
Journal of nuclear materials 526, 151767 - () [10.1016/j.jnucmat.2019.151767]  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

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Argon-seeded plasma exposure and oxidation performance of tungsten-chromium-yttrium smart alloys
Tungsten 1, 2 () [10.1007/s42864-019-00016-7] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Insight into single-fiber push-out test of tungsten fiber-reinforced tungsten
Composite interfaces 26(2), 107 - 126 () [10.1080/09276440.2018.1475696] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Hydrogen isotope ratios measurements by Penning gauge spectroscopy of molecular Fulcher-α band
Fusion engineering and design 146(Part A), 1325 - 1328 () [10.1016/j.fusengdes.2019.02.068] BibTeX | EndNote: XML, Text | RIS

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Performance Estimation of Beryllium Under ITER Relevant Transient Thermal Loads
Nuclear materials and energy 18, 291 - 296 () [10.1016/j.nme.2018.12.026] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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High Resolution Probe for filament transport and current density study at the edge region of W7-X
Journal of Instrumentation 14(09), C09035 - C09035 () [10.1088/1748-0221/14/09/C09035]  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

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Analysis of deposited layers with deuterium and impurity elements on samples from the divertor of JET with ITER-like wall
Journal of nuclear materials 516, 202 - 213 () [10.1016/j.jnucmat.2018.11.027] BibTeX | EndNote: XML, Text | RIS

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First divertor physics studies in Wendelstein 7-X
Nuclear fusion 59(9), 096014 - () [10.1088/1741-4326/ab280f] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Evaluation of the high temperature oxidation of W-Cr-Zr self-passivating alloys
Corrosion science 147, 201 - 211 () [10.1016/j.corsci.2018.11.022] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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COREDIV numerical simulation of high neutron rate JET-ILW DD pulses in view of extension to JET-ILW DT experiments
Nuclear fusion 59(5), 056026 - () [10.1088/1741-4326/ab0c47]  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

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Μicro-Structured Tungsten: an AdvancedPplasma-Facing Material
Nuclear materials and energy 19, 7 - 12 () [10.1016/j.nme.2019.02.007] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Characteristics of plasma flow profiles in a super-X-divertor-like configuration
Nuclear materials and energy 19, 149 - 154 () [10.1016/j.nme.2019.02.016] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Self-consistent simulation of supersonic plasma flows in advanced divertors
Nuclear fusion 59(7), 076041 - () [10.1088/1741-4326/ab1f2c] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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An assessment of the first wall and limiter erosion during limiter discharge stages in DEMO
Nuclear fusion 59(7), 076002 - () [10.1088/1741-4326/ab1434]  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

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Simulation of Spectra Code (SOS) for ITER Active Beam Spectroscopy
Atoms 7(1), 30 - () [10.3390/atoms7010030] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Oxide Dispersion Strengthened Bond Coats with Higher Alumina Content: Oxidation Resistance and Influence on Thermal Barrier Coating Lifetime
Oxidation of metals 92(3-4), 167-194 () [10.1007/s11085-019-09931-z] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Recent advances in EAST physics experiments in support of steady-state operation for ITER and CFETR
Nuclear fusion 59(11), 112003 - () [10.1088/1741-4326/ab0396] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Advances in plasma–wall interaction control for H-mode operation over 100 s with ITER-like tungsten divertor on EAST
Nuclear fusion 59(8), 086036 - () [10.1088/1741-4326/ab1ed4] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Formation of the non-axisymmetric helical current driven by a biased electrode in the scrape-off layer on J-TEXT
Nuclear fusion 59(9), 096047 - () [10.1088/1741-4326/ab2d03] BibTeX | EndNote: XML, Text | RIS

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Spectroscopic studies of fuel recycling and impurity behaviors in the divertor region of Wendelstein 7-X
Plasma science & technology 21(10), 105102 - () [10.1088/2058-6272/ab273b] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Development and Performance of Tungsten-Coated Graphitic Foam for Plasma-Facing Components
Fusion engineering and design 75(6)(6), 551-557 () [10.1080/15361055.2019.1607706] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Preliminary design of the island divertor coils on the J-TEXT tokamak
Fusion engineering and design 146, 902 - 905 () [10.1016/j.fusengdes.2019.01.109] Embargoed OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Laser-Induced Desorption of co-deposited Deuterium in Beryllium Layers on Tungsten
Nuclear materials and energy 19, 503 - 509 () [10.1016/j.nme.2019.04.007] OpenAccess  Download fulltext Files  Download fulltextFulltext by OpenAccess repository BibTeX | EndNote: XML, Text | RIS

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Fuel Retention Diagnostic Setup (FREDIS) for desorption of gases from beryllium and tritium containing samples
Fusion engineering and design 146(Part A), 1176 - 1180 () [10.1016/j.fusengdes.2019.02.035] BibTeX | EndNote: XML, Text | RIS

Letzte Änderung: 26.11.2021