Publications 2019
Articles in refereed journals 2019
Simulation of magnetic control of the plasma shape on the DEMO tokamak
Fusion engineering and design 146(Part A), 728 - 731 (2019) [10.1016/j.fusengdes.2019.01.065]
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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 (2019) [10.1016/j.nme.2019.03.005]
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Diagnostics for plasma control – From ITER to DEMO
Fusion engineering and design 146(Part A), 465 - 472 (2019) [10.1016/j.fusengdes.2018.12.092]
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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 (2019) [10.1016/j.nme.2019.03.016]
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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 (2019) [10.1016/j.nme.2018.12.004]
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Erosion, screening, and migration of tungsten in the JET divertor
Nuclear fusion 59(9), 096035 - (2019) [10.1088/1741-4326/ab2aef]
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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 - (2019) [10.1063/1.5054279]
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Pre-conceptual study of the European DEMO neutron diagnostics
Journal of Instrumentation 14(09), C09001 - C09001 (2019) [10.1088/1748-0221/14/09/C09001]
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Materials development for new high heat-flux component mock-ups for DEMO
Fusion engineering and design 146, 1431 - 1436 (2019) [10.1016/j.fusengdes.2019.02.098]
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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 (2019) [10.1016/j.fusengdes.2018.12.031]
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Measurement of the Magnetic Field in a Linear Magnetized Plasma by Tunable Diode Laser Absorption Spectroscopy
Atoms 7(2), 48 - (2019) [10.3390/atoms7020048]
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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 - (2019) [10.1063/1.5088931]
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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 (2019) [10.1016/j.fusengdes.2019.03.188]
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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 (2019) [10.1016/j.nme.2019.01.006]
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Investigation of hydrogen isotope retention mechanisms in beryllium: High resolution TPD measurements
Nuclear materials and energy 19, 440 - 444 (2019) [10.1016/j.nme.2019.03.018]
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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 (2019) [10.1016/j.nme.2019.02.006]
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Plastic deformation of tungsten due to deuterium plasma exposure: Insights from micro-compression tests
Scripta materialia 162, 132 - 135 (2019) [10.1016/j.scriptamat.2018.10.052]
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Overview of the DEMO staged design approach in Europe
Nuclear fusion 59(6), 066013 - (2019) [10.1088/1741-4326/ab1178]
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Methods for quantitative study of divertor heat loads on W7-X
Nuclear fusion 59(6), 066007 - (2019) [10.1088/1741-4326/ab0f49]
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Effects of toroidal plasma current on divertor power depositions on Wendelstein 7-X
Nuclear fusion 59(10), 106015 - (2019) [10.1088/1741-4326/ab32c2]
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Conceptual studies on spectroscopy and radiation diagnostic systems for plasma control on DEMO
Fusion engineering and design 146, 2297 - 2301 (2019) [10.1016/j.fusengdes.2019.03.176]
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Development of glow discharge and electron cyclotron resonance heating conditioning on W7-X
Nuclear materials and energy 18, 227 - 232 (2019) [10.1016/j.nme.2018.12.010]
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Influence of thermal shocks on the He induced surface morphology on tungsten
Nuclear materials and energy 18, 321 - 325 (2019) [10.1016/j.nme.2019.01.029]
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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 (2019) [10.1016/j.nme.2019.03.013]
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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 - (2019) [10.3390/condmat4010029]
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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 (2019) [10.1016/j.nme.2018.12.012]
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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 (2019) [10.1016/j.surfcoat.2019.03.017]
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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 (2019) [10.1016/j.compositesb.2018.11.078]
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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 (2019) [10.1016/j.nme.2019.01.030]
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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 - (2019) [10.1088/1741-4326/ab1a79]
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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 (2019) [10.1016/j.nme.2018.12.009]
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Detailed structural analysis of a graded TF coil winding pack for EU DEMO
Fusion engineering and design 146, 535 - 538 (2019) [10.1016/j.fusengdes.2019.01.016]
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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 (2019) [10.1016/j.fusengdes.2018.11.044]
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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 - (2019) [10.1063/1.5100093]
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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 (2019) [10.1016/j.nme.2019.01.004]
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Sublimation of advanced tungsten alloys under DEMO relevant accidental conditions
Fusion engineering and design 146(Part A), 1198-1202 (2019) [10.1016/j.fusengdes.2019.02.039]
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Overview of first Wendelstein 7-X high-performance operation
Nuclear fusion 59(11), 112004 - (2019) [10.1088/1741-4326/ab03a7]
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Plug flow reactor model of the plasma chemical conversion of CO2
Plasma sources science and technology 28(9), 095002 (2019) [10.1088/1361-6595/ab3774]
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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 - (2019) [10.1088/1361-6587/ab0624]
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Influence of plasma impurities on the fuel retention in tungsten
Nuclear fusion 59(8), 086029 - (2019) [10.1088/1741-4326/ab235d]
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Design status of the ITER core CXRS diagnostic setup
Fusion engineering and design 146(Part A), 228 - 231 (2019) [10.1016/j.fusengdes.2018.12.026]
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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 (2019) [10.1016/j.nme.2019.03.001]
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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 - (2019) [10.1088/1741-4326/ab3a79]
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Overview of the recent experimental research on the J-TEXT tokamak
Nuclear fusion 59(11), 112016 - (2019) [10.1088/1741-4326/ab1a72]
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Optimization of single crystal mirrors for ITER diagnostics
Fusion engineering and design 146, 1450 - 1453 (2019) [10.1016/j.fusengdes.2019.02.102]
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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 - (2019) [10.1088/1741-4326/ab0d29]
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High Pulse Numbe Thermal Shock Testing of Tungsten Alloys Produced by Powder Injection Molding
Nuclear materials and energy 20, 100680 (2019) [10.1016/j.nme.2019.100680]
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Implications of uncertainties on European DEMO design
Nuclear fusion 59(6), 066012 - (2019) [10.1088/1741-4326/ab13e2]
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On the nature of carbon embrittlement of tungsten fibers during powder metallurgical processes
Fusion engineering and design 145, 18 - 22 (2019) [10.1016/j.fusengdes.2019.05.033]
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Fracture behavior of random distributed short tungsten fiber-reinforced tungsten composites
Nuclear fusion 59(8), 086034 - (2019) [10.1088/1741-4326/ab25b0]
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Emission of Fast Hydrogen Atoms in a Low Density Gas Discharge—The Most “Natural” Mirror Laboratory
Atoms 7(3), 81 - (2019) [10.3390/atoms7030081]
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Modeling of H/D isotope-exchange in crystalline beryllium
Nuclear materials and energy 20, 100682 - (2019) [10.1016/j.nme.2019.100682]
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Bolometer developments in diagnostics for magnetic confinement fusion
Journal of Instrumentation 14(10), C10004 - C10004 (2019) [10.1088/1748-0221/14/10/C10004]
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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 (2019) [10.1007/s10894-018-0202-1]
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On the use of rhodium mirrors for optical diagnostics in ITER
Fusion engineering and design 146(B), 2514-2518 (2019) [10.1016/j.fusengdes.2019.04.031]
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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 (2019) [10.1016/j.fusengdes.2018.11.009]
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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 (2019) [10.1016/j.nme.2018.12.008]
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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 (2019) [10.1016/j.nme.2018.12.019]
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First results from divertor operation in Wendelstein 7-X
Plasma physics and controlled fusion 61(1), 014035 - (2019) [10.1088/1361-6587/aaec25]
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Long-lived coupled peeling ballooning modes preceding ELMs on JET
Nuclear fusion 59(5), 056004 - (2019) [10.1088/1741-4326/ab0031]
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European materials development: Results and perspective
Fusion engineering and design 146, 1300 - 1307 (2019) [10.1016/j.fusengdes.2019.02.063]
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Diffusion model of the impact of helium and argon impurities on deuterium retention in tungsten
Nuclear fusion 59(4), 046004 - (2019) [10.1088/1741-4326/aafe8d]
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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 (2019) [10.1016/j.jcp.2018.07.051]
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Model discovery for studies of surface morphological modifications based on Kuramoto-Sivashinsky dynamics
Physical review / E 100(3), 033312 (2019) [10.1103/PhysRevE.100.033312]
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Beryllium global erosion and deposition at JET-ILW simulated with ERO2.0
Nuclear materials and energy 18, 331 - 338 (2019) [10.1016/j.nme.2019.01.015]
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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 - (2020) [10.1002/ctpp.201900149]
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Preferential sputtering induced Cr-Diffusion during plasma exposure of WCrY smart alloys
Journal of nuclear materials 526, 151767 - (2019) [10.1016/j.jnucmat.2019.151767]
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Argon-seeded plasma exposure and oxidation performance of tungsten-chromium-yttrium smart alloys
Tungsten 1, 2 (2019) [10.1007/s42864-019-00016-7]
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Insight into single-fiber push-out test of tungsten fiber-reinforced tungsten
Composite interfaces 26(2), 107 - 126 (2019) [10.1080/09276440.2018.1475696]
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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 (2019) [10.1016/j.fusengdes.2019.02.068]
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Performance Estimation of Beryllium Under ITER Relevant Transient Thermal Loads
Nuclear materials and energy 18, 291 - 296 (2019) [10.1016/j.nme.2018.12.026]
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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 (2019) [10.1088/1748-0221/14/09/C09035]
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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 (2019) [10.1016/j.jnucmat.2018.11.027]
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First divertor physics studies in Wendelstein 7-X
Nuclear fusion 59(9), 096014 - (2019) [10.1088/1741-4326/ab280f]
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Evaluation of the high temperature oxidation of W-Cr-Zr self-passivating alloys
Corrosion science 147, 201 - 211 (2019) [10.1016/j.corsci.2018.11.022]
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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 - (2019) [10.1088/1741-4326/ab0c47]
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Μicro-Structured Tungsten: an AdvancedPplasma-Facing Material
Nuclear materials and energy 19, 7 - 12 (2019) [10.1016/j.nme.2019.02.007]
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Characteristics of plasma flow profiles in a super-X-divertor-like configuration
Nuclear materials and energy 19, 149 - 154 (2019) [10.1016/j.nme.2019.02.016]
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Self-consistent simulation of supersonic plasma flows in advanced divertors
Nuclear fusion 59(7), 076041 - (2019) [10.1088/1741-4326/ab1f2c]
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An assessment of the first wall and limiter erosion during limiter discharge stages in DEMO
Nuclear fusion 59(7), 076002 - (2019) [10.1088/1741-4326/ab1434]
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Simulation of Spectra Code (SOS) for ITER Active Beam Spectroscopy
Atoms 7(1), 30 - (2019) [10.3390/atoms7010030]
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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 (2019) [10.1007/s11085-019-09931-z]
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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 - (2019) [10.1088/1741-4326/ab0396]
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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 - (2019) [10.1088/1741-4326/ab1ed4]
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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 - (2019) [10.1088/1741-4326/ab2d03]
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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 - (2019) [10.1088/2058-6272/ab273b]
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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 (2019) [10.1080/15361055.2019.1607706]
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Preliminary design of the island divertor coils on the J-TEXT tokamak
Fusion engineering and design 146, 902 - 905 (2019) [10.1016/j.fusengdes.2019.01.109]
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Laser-Induced Desorption of co-deposited Deuterium in Beryllium Layers on Tungsten
Nuclear materials and energy 19, 503 - 509 (2019) [10.1016/j.nme.2019.04.007]
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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 (2019) [10.1016/j.fusengdes.2019.02.035]
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