Publikationen 2017
Beiträge in referierten Zeitschriften 2017
Assessment of SOLPS5.0 divertor solutions with drifts and currents against L-mode experiments in ASDEX Upgrade and JET
Plasma physics and controlled fusion 59(3), 035003 - (2017) [10.1088/1361-6587/59/3/035003]
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Initial definition of structural load conditions in DEMO
Fusion engineering and design 124, 633 - 637 (2017) [10.1016/j.fusengdes.2017.02.061]
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Investigations of the first-wall erosion of DEMO with the CELLSOR code
Nuclear materials and energy 12, 1163 - 1170 (2017) [10.1016/j.nme.2017.01.006]
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Power exhaust by SOL and pedestal radiation at ASDEX Upgrade and JET
Nuclear materials and energy 12, 111-118 (2017) [10.1016/j.nme.2016.12.029]
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Comment on ‘On the fusion triple product and fusion power gain of tokamak pilot plants and reactors’, by A. Costley
Nuclear fusion 57(3), 038001 - (2017) [10.1088/1741-4326/aa4f51]
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Systems code studies on the optimization of design parameters for a pulsed DEMO tokamak reactor
Fusion engineering and design 123, 206 - 211 (2017) [10.1016/j.fusengdes.2017.01.009]
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Making ICRF power compatible with a high-Z wall in ASDEX Upgrade
Plasma physics and controlled fusion 59(1), 014022 - (2017) [10.1088/0741-3335/59/1/014022]
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ERO modeling of beryllium erosion by helium plasma in experiments at PISCES-B
Nuclear materials and energy 12, 1157-1162 (2017) [10.1016/j.nme.2017.05.004]
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Intra-ELM tungsten sputtering in JET ITER-like wall: analytical studies of Be impurity and ELM type influence
Physica scripta T170, 014065 - (2017) [10.1088/1402-4896/aa90c7]
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Surface modification of He pre-exposed tungsten samples by He plasma impact in the divertor manipulator of ASDEX Upgrade
Nuclear materials and energy 12, 575-581 (2017) [10.1016/j.nme.2016.11.002]
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Plasma–wall interaction studies within the EUROfusion consortium: progress on plasma-facing components development and qualification
Nuclear fusion 57(11), 116041 - (2017) [10.1088/1741-4326/aa796e]
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Spectroscopic determination of inverse photon efficiencies of W atoms in the scrape-off layer of TEXTOR
Physica scripta T170, 014052 - (2017) [10.1088/1402-4896/aa8a45]
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2016 Nuclear Fusion prize acceptance speech
Nuclear fusion 57(1), 010204 - (2017) [10.1088/1741-4326/57/1/010204]
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Surface modifications and deuterium retention in polycrystalline and single crystal tungsten as a function of particle flux and temperature
Journal of nuclear materials 495, 211 - 219 (2017) [10.1016/j.jnucmat.2017.08.026]
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Response of tungsten surfaces to helium and hydrogen plasma exposure under ITER relevant steady state and repetitive transient conditions
Nuclear fusion 57, 12 (2017) [10.1088/1741-4326/aa81e4]
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The comparison between modeling of edge localized modes with a current relaxation model and experiment on EAST
Plasma physics and controlled fusion 59(8), 085010 (2017) [10.1088/1361-6587/aa7360]
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Self-passivating W-Cr-Y alloys: Characterization and testing
Fusion engineering and design 124, 1118-1121 (2017) [10.1016/j.fusengdes.2017.03.001]
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Progress in EU-DEMO in-vessel components integration
Fusion engineering and design 124, 562 - 566 (2017) [10.1016/j.fusengdes.2017.03.147]
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Plasma-wall interaction of advanced materials
Nuclear materials and energy 12, 307-312 (2017) [10.1016/j.nme.2016.10.008]
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Transient induced tungsten melting at the Joint European Torus (JET)174
Physica scripta T170, 014013 - (2017) [10.1088/1402-4896/aa8789]
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Thermal analysis of protruding surfaces in the JET divertor
Nuclear fusion 57(6), 066009 - (2017) [10.1088/1741-4326/aa687e]
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Preparation of erosion and deposition investigations on plasma facing components in Wendelstein 7-X
Physica scripta 2017(T170), 014010 - (2017) [10.1088/1402-4896/aa86fb]
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Advances in understanding of high- Z material erosion and re-deposition in low- Z wall environment in DIII-D
Nuclear fusion 57(5), 056016 - (2017) [10.1088/1741-4326/aa6451]
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Detection of ammonia by residual gas analysis in AUG and JET
Fusion engineering and design 124, 239-243 (2017) [10.1016/j.fusengdes.2017.05.037]
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Measurement of the plasma edge profiles using the combined probe on W7-X
Nuclear fusion 57(12), 126020 - (2017) [10.1088/1741-4326/aa8385]
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Sub-surface microstructure of single and polycrystalline tungsten after high flux plasma exposure studied by TEM
Applied surface science 393, 330 - 339 (2017) [10.1016/j.apsusc.2016.09.071]
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The role of the density profile in the ASDEX-Upgrade pedestal structure
Plasma physics and controlled fusion 59(1), 014017 (2017) [10.1088/0741-3335/59/1/014017]
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Numerical investigation of plasma edge transport and limiter heat fluxes in Wendelstein 7-X startup plasmas with EMC3-EIRENE
Nuclear fusion 57(3), 036021 - (2017) [10.1088/1741-4326/aa4f83]
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Overview of progress in European medium sized tokamaks towards an integrated plasma-edge/wall solution
Nuclear fusion 57(10), 102014 (2017) [10.1088/1741-4326/aa6084]
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ERO modelling of tungsten erosion in the linear plasma device PSI-2
Nuclear materials and energy 12, 253-260 (2017) [10.1016/j.nme.2017.03.014]
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ERO modeling of Cr sputtering in the linear plasma device PSI-2
Physica scripta T170, 014051 - (2017) [10.1088/1402-4896/aa8ff3]
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Thin film proton conducting membranes for micro-solid oxide fuel cells by chemical solution deposition
Thin solid films 636, 446 - 457 (2017) [10.1016/j.tsf.2017.06.038]
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European DEMO design strategy and consequences for materials
Nuclear fusion 57(9), 092002 - (2017) [10.1088/1741-4326/57/9/092002]
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Monte-Carlo fluid approaches to detached plasmas in non-axisymmetric divertor configurations
Plasma physics and controlled fusion 59(3), 034006 - (2017) [10.1088/1361-6587/59/3/034006]
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Heating & current drive efficiencies, TBR and RAMI considerations for DEMO
Fusion engineering and design 123, 495 - 499 (2017) [10.1016/j.fusengdes.2017.02.007]
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Reconstruction of recycling flux from synthetic camera images, evaluated for the Wendelstein 7-X startup limiter
Nuclear fusion 57(12), 126022 - (2017) [10.1088/1741-4326/aa8515]
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Experimental and numerical studies of the shutter dynamics for the ITER core CXRS diagnostic
Fusion engineering and design 123, 722-726 (2017) [10.1016/j.fusengdes.2017.05.099]
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Interplay of light and heavy impurities in a fusion device
Plasma physics and controlled fusion 59(2), 025001 - (2017) [10.1088/1361-6587/59/2/025001]
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Key issues for long-pulse high- β N operation with the Experimental Advanced Superconducting Tokamak (EAST)
Nuclear fusion 57(5), 056021 - (2017) [10.1088/1741-4326/aa626c]
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Tensile deformation behavior of tungsten fibre-reinforced tungsten composite specimens in as-fabricated state
Fusion engineering and design 124, 396 - 400 (2017) [10.1016/j.fusengdes.2017.02.054]
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Realization of minute-long steady-state H-mode discharges on EAST
Plasma science & technology 19(3), 032001 - (2017) [10.1088/2058-6272/19/3/032001]
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Ion cyclotron resonance heating for tungsten control in various JET H-mode scenarios
Plasma physics and controlled fusion 59(5), 055001 (2017) [10.1088/1361-6587/aa60d2]
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Main chamber wall plasma loads in JET-ITER-like wall at high radiated fraction
Nuclear materials and energy 12, 234 - 240 (2017) [10.1016/j.nme.2017.02.010]
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Plasma-wall interaction studies in the full-W ASDEX upgrade during helium plasma discharges
Nuclear fusion 57(6), 066015 (2017) [10.1088/1741-4326/aa69c4]
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Damage and deuterium retention of re-solidified tungsten following vertical displacement event-like heat load
Nuclear materials and energy 12, 1303 - 1307 (2017) [10.1016/j.nme.2016.11.003]
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Long-term fuel retention and release in JET ITER-Like Wall at ITER-relevant baking temperatures
Nuclear fusion 57(8), 086024 - (2017) [10.1088/1741-4326/aa747e]
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Confinement in Wendelstein 7-X limiter plasmas
Nuclear fusion 57(8), 086010 - (2017) [10.1088/1741-4326/aa7372]
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Development of laser-based technology for the routine first wall diagnostic on the tokamak EAST: LIBS and LIAS
Physica scripta T170, 014046 - (2017) [10.1088/1402-4896/aa8650]
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Analysis of anisotropic effects on energy induced by lower hybrid wave heating on EAST
Plasma physics and controlled fusion 59(6), 065010 (2017) [10.1088/1361-6587/aa6988]
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Thomson scattering of plasma turbulence on PSI-2
Nuclear materials and energy 12, 1253 - 1258 (2017) [10.1016/j.nme.2016.12.006]
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Scaling for the SOL/separatrix χ ⊥ following from the heuristic drift model for the power scrape-off layer width
Plasma physics and controlled fusion 59(6), 064007 - (2017) [10.1088/1361-6587/aa6ab9]
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The effect of the isotope on the H-mode density limit
Nuclear fusion 57(8), 086007 - (2017) [10.1088/1741-4326/aa663a]
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Response of the imaging cameras to hard radiation during JET operation
Fusion engineering and design 123, 669-673 (2017) [10.1016/j.fusengdes.2017.03.167]
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JUVIL: A new innovative software framework for data analysis of JET imaging systems intended for the study of plasma physics and machine operational safety
Fusion engineering and design 123, 979-985 (2017) [10.1016/j.fusengdes.2017.03.005]
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Digital twin applications for the JET divertor
Fusion engineering and design 125, 71 - 76 (2017) [10.1016/j.fusengdes.2017.10.012]
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Edge localized mode control using n = 1 resonant magnetic perturbation in the EAST tokamak
Nuclear fusion 57(3), 036007 - (2017) [10.1088/1741-4326/57/3/036007]
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Design and development of a LIBS system on linear plasma device PSI-2 for in situ real-time diagnostics of plasma-facing materials
Nuclear materials and energy 12, 1224 - 1230 (2017) [10.1016/j.nme.2016.11.021]
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Overview of ASDEX Upgrade results
Nuclear fusion 57(10), 102015 - (2017) [10.1088/1741-4326/aa64f6]
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Dealing with uncertainties in fusion power plant conceptual development
Nuclear fusion 57(4), 046024 - (2017) [10.1088/1741-4326/aa5e2c]
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The near infrared imaging system for the real-time protection of the JET ITER-like wall
Physica scripta T170, 014027 (2017) [10.1088/1402-4896/aa8a14]
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Modelling of deposition and erosion of injected WF 6 and MoF 6 in TEXTOR
Nuclear materials and energy 12, 564 - 568 (2017) [10.1016/j.nme.2016.10.022]
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Beryllium Layer Response to ITER-Like ELM Plasma Pulses in QSPA-Be
Nuclear materials and energy 12, 433 - 440 (2017) [10.1016/j.nme.2017.01.012]
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Performance and properties of the first plasmas of Wendelstein 7-X
Plasma physics and controlled fusion 59(1), 014018 - (2017) [10.1088/0741-3335/59/1/014018]
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Particle conservation in numerical models of the tokamak plasma edge
Physics of plasmas 24(4), 042511 - (2017) [10.1063/1.4980858]
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Can gas puff be used for cleaning of the diagnostic first mirrors in ITER?4
Fusion engineering and design 123, 834 - 837 (2017) [10.1016/j.fusengdes.2017.03.166]
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Investigation of turbulence rotation in limiter plasmas at W7-X with newly installed poloidal correlation reflectometer
Nuclear fusion 57(6), 066023 - (2017) [10.1088/1741-4326/aa66ae]
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Specific design and structural issues of single crystalline first mirrors for diagnostics
Fusion engineering and design 124, 548-552 (2017) [10.1016/j.fusengdes.2017.04.038]
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Argon impurity transport studies at Wendelstein 7-X using x-ray imaging spectrometer measurements
Nuclear fusion 57(8), 086013 - (2017) [10.1088/1741-4326/aa70f4]
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Longitudinal and shear wave velocities in pure tungsten and tungsten fiber-reinforced tungsten composites
Physica scripta T170, 014024 - (2017) [10.1088/1402-4896/aa89c7]
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Laser-induced breakdown spectroscopy for Wendelstein 7-X stellarator limiter tile analysis
Physica scripta T170, 014004 - (2017) [10.1088/0031-8949/2017/T170/014004]
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Toroidal modeling of plasma response to RMP fields in ITER
Plasma physics and controlled fusion 59(4), 044005 - (2017) [10.1088/1361-6587/aa5769]
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Diagnostic set-up and modelling for investigation of synergy between 3D edge physics and plasma-wall interactions on Wendelstein 7-X
Nuclear fusion 57(6), 066049 (2017) [10.1088/1741-4326/aa6cde]
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Development of advanced high heat flux and plasma-facing materials
Nuclear fusion 57(9), 092007 (2017) [10.1088/1741-4326/aa6f71]
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Material testing facilities and programs for PFC testing
Nuclear fusion 57(9), 092012 (2017) [10.1088/1741-4326/aa4feb]
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Overview of the JET results in support to ITER
Nuclear fusion 57(10), 102001 (2017) [10.1088/1741-4326/aa5e28]
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Advanced smart tungsten alloys for a future fusion power plant
Plasma physics and controlled fusion 59(6), 064003 - (2017) [10.1088/1361-6587/aa6948]
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Smart alloys for a future fusion power plant: First studies under stationary plasma load and in accidental conditions
Nuclear materials and energy 12, 1363-1367 (2017) [10.1016/j.nme.2016.11.015]
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Smart tungsten alloys as a material for the first wall of a future fusion power plant
Nuclear fusion 57(6), 066020 - (2017) [10.1088/1741-4326/aa6816]
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First direct comparative test of single crystal rhodium and molybdenum mirrors for ITER diagnostics
29th Symposium on Fusion Technology (SOFT 2016), PraguePrague, Czech Republic, 5 Sep 2016 - 9 Sep 2016
Fusion engineering and design 123, 674-677 (2017) [10.1016/j.fusengdes.2017.03.053]
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New oxidation-resistant tungsten alloys for use in the nuclear fusion reactors
Physica scripta T170, 014012 - (2017) [10.1088/1402-4896/aa81f5]
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Design of an ICRF system for plasma–wall interactions and RF plasma production studies on TOMAS
Fusion engineering and design 123, 317-320 (2017) [10.1016/j.fusengdes.2017.04.123]
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Uncertainties in power plant design point evaluations
Fusion engineering and design 123, 63 - 66 (2017) [10.1016/j.fusengdes.2017.01.029]
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Stability and propagation of the high field side high density front in the fluctuating state of detachment in ASDEX Upgrade
Nuclear materials and energy 12, 1152-1156 (2017) [10.1016/j.nme.2016.10.002]
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The influence of annealing on yttrium oxide thin film deposited by reactive magnetron sputtering: Process and microstructure
Nuclear materials and energy 10, 1 - 8 (2017) [10.1016/j.nme.2016.12.031]
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Development and characterization of powder metallurgically produced discontinuous tungsten fiber reinforced tungsten composites
Physica scripta 2017, 7 / 014005 (2017) [10.1088/0031-8949/2017/T170/014005]
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Angular and velocity distributions of tungsten sputtered by low energy argon ions
Journal of nuclear materials 496, 18 - 23 (2017) [10.1016/j.jnucmat.2017.09.021]
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Deuterium retention in RAFM steels after high fluence plasma expo
Nuclear materials and energy 12, 648-654 (2017) [10.1016/j.nme.2017.05.005]
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Dynamic outgassing of deuterium, helium and nitrogen from plasma-facing materials under DEMO relevant conditions
Nuclear fusion 57(1), 016020 - (2017) [10.1088/0029-5515/57/1/016020]
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Analytical continuous slowing down model for nuclear reaction cross-section measurements by exploitation of stopping for projectile energy scanning and results for $_{13}$C($_{3}$He,α)$_{12}$C and $_{13}$C($_{3}$He,p)$_{15}$N
Nuclear instruments & methods in physics research / B 394, 134 - 140 (2017) [10.1016/j.nimb.2017.01.017]
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On the mechanisms governing gas penetration into a tokamak plasma during a massive gas injection
Nuclear fusion 57(1), 016027 - (2017) [10.1088/0029-5515/57/1/016027]
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Investigations on tungsten heavy alloys for use as plasma facing material
Fusion engineering and design 124, 450 - 454 (2017) [10.1016/j.fusengdes.2017.01.043]
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Determination of divertor stray light in high-resolution main chamber H α spectroscopy in JET-ILW
Nuclear fusion 57(1), 016031 - (2017) [10.1088/0029-5515/57/1/016031]
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A multi-purpose manipulator system for W7-X as user facility for plasma edge investigation
29th Symposium on Fusion Technology (SOFT 2016), PragPrag, Tschechoslowakai, 5 Sep 2016 - 9 Sep 2016
Fusion engineering and design 123, 960-964 (2017) [10.1016/j.fusengdes.2017.03.013]
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Low-energy collisions between electrons and BeH + : Cross sections and rate coefficients for all the vibrational states of the ion
Atomic data and nuclear data tables 115-116, 287 - 308 (2017) [10.1016/j.adt.2016.09.002]
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Surface modification and deuterium retention in reduced-activation steels under low-energy deuterium plasma exposure. Part II: steels pre-damaged with 20 MeV W ions and high heat flux
Nuclear fusion 57(3), 036011 - (2017) [10.1088/1741-4326/57/3/036011]
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Self-castellation of tungsten monoblock under high heat flux loading and impact of material properties
Nuclear materials and energy 12, 200-204 (2017) [10.1016/j.nme.2016.10.025]
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Mechanical pre-dimensioning and pre-optimization of the tokamaks’ toroidal coils featuring the winding pack layout
Fusion engineering and design 124, 77-81 (2017) [10.1016/j.fusengdes.2017.04.065]
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SOL parallel momentum loss in ASDEX Upgrade and comparison with SOLPS
Nuclear materials and energy 12, 181-186 (2017) [10.1016/j.nme.2017.01.026]
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Magnetic field pitch angle and perpendicular velocity measurements from multi-point time-delay estimation of poloidal correlation reflectometry
Plasma physics and controlled fusion 59(2), 025013 - (2017) [10.1088/1361-6587/59/2/025013]
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A fluid-kinetic approach for 3D plasma edge transport in He plasma
Nuclear fusion 57(5), 056011 - (2017) [10.1088/1741-4326/aa60e4]
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Evidence and modeling of 3D divertor footprint induced by lower hybrid waves on EAST with tungsten divertor operations
Nuclear fusion 57(12), 126054 - (2017) [10.1088/1741-4326/aa8bf3]
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The microstructure of tungsten exposed to D plasma with different impurities
Nuclear materials and energy 12, 302-306 (2017) [10.1016/j.nme.2016.11.001]
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The microstructure of reduced activation ferritic/martensitic (RAFM) steels exposed to D plasma with different seeding impurities
Physica scripta T170, 014036 - (2017) [10.1088/1402-4896/aa8de5]
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Influence of non-local thermodynamic equilibrium and Zeeman effects on magnetic equilibrium reconstruction using spectral motional Stark effect diagnostic
Review of scientific instruments 88(8), 083509 (2017) [10.1063/1.4994889]
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The high field side high density region in SOLPS-modeling of nitrogen-seeded H-modes in ASDEX Upgrade
Nuclear materials and energy 12, 193-199 (2017) [10.1016/j.nme.2017.01.010]
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Expanding the role of impurity spectroscopy for investigating the physics of high-Z dissipative divertors
Nuclear materials and energy 12, 91-99 (2017) [10.1016/j.nme.2016.12.003]
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Drift-based scrape-off particle width in X-point geometry
Nuclear fusion 57(4), 046011 - (2017) [10.1088/1741-4326/aa5ab7]
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Plasma-wall interactions in the presence of plasma fluctuations—interpretation of line emission from sputtered tungsten in PSI-2
Physica scripta T170, 014039 - (2017) [10.1088/1402-4896/aa8db2]
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Realization of High Heat Flux Tungsten Monoblock Type Target With Graded Interlayer for Application to DEMO Divertor
Physica scripta T170, 014022 - (2017) [10.1088/1402-4896/aa8b02]
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Tensile behaviour of drawn tungsten wire used in tungsten fibre-reinforced tungsten composites
Physica scripta T170, 014032 - (2017) [10.1088/1402-4896/aa891d]
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First ERO2.0 modeling of Be erosion and non-local transport in JET ITER-like wall
Physica scripta T170, 014018 - (2017) [10.1088/1402-4896/aa89ca]
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Development of a hybrid kinetic-fluid model for line radiation transport in magnetic fusion plasmas
High energy density physics 22, 73 - 76 (2017) [10.1016/j.hedp.2017.02.012]
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Fuel inventory and deposition in castellated structures in JET-ILW
Nuclear fusion 57(6), 066027 (2017) [10.1088/1741-4326/aa6864]
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Overview of wall probes for erosion and deposition studies in the TEXTOR tokamak
Matter and radiation at extremes 2(3), 87 - 104 (2017) [10.1016/j.mre.2017.03.002]
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Preparing the future post-mortem analysis of beryllium-based JET and ITER samples by multi-wavelengths Raman spectroscopy on implanted Be, and co-deposited Be
Nuclear fusion 57(7), 076035 (2017) [10.1088/1741-4326/aa70bb]
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Surface morphology of tungsten exposed to helium plasma at temperatures below fuzz formation threshold 1073 K
Nuclear fusion 57(1), 016040 - (2017) [10.1088/1741-4326/57/1/016040]
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Surface morphology in tungsten and RAFM steel exposed to helium plasma in PSI-2
Physica scripta T170, 014062 - (2017) [10.1088/1402-4896/aa93a2]
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A PCS7-based control and safety system for operation of the W7-X Multi-Purpose Manipulator facility
Fusion engineering and design 123, 699 - 702 (2017) [10.1016/j.fusengdes.2017.05.125]
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Experimental data on low energy electron impact ionisation of W
Physica scripta T170, 014075 - (2017) [10.1088/1402-4896/aa9239]
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Development of an ICRH antenna system at W7-X for plasma heating and wall conditioning
29th Symposium on Fusion Technology (SOFT 2016), PraguePrague, Czech Republic, 5 Sep 2016 - 9 Sep 2016
Fusion engineering and design 123, 303-308 (2017) [10.1016/j.fusengdes.2017.05.019]
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VUV spectroscopy in impurity injection experiments at KSTAR using prototype ITER VUV spectrometer
Review of scientific instruments 88(8), 083511 - (2017) [10.1063/1.4998970]
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Design of ITER divertor VUV spectrometer and prototype test at KSTAR tokamak
The European physical journal / D Atomic, molecular, optical and plasma physics D 71(12), 313 (2017) [10.1140/epjd/e2017-70825-3]
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Quartz micro-balance results of pulse-resolved erosion/deposition in the JET-ILW divertor
Nuclear materials and energy 12, 478-482 (2017) [10.1016/j.nme.2017.03.007]
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Improving accuracy of Penning gauge spectroscopy for the determination of hydrogen isotope H/D ratios
Fusion engineering and design 123, 906-910 (2017) [10.1016/j.fusengdes.2017.03.092]
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In-situ mass-spectrometer of magnetized plasmas
Nuclear materials and energy 12, 1243-1247 (2017) [10.1016/j.nme.2017.01.015]
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High Pulse Number transient heat loads on beryllium
Nuclear materials and energy 12, 1184 - 1188 (2017) [10.1016/j.nme.2016.11.032]
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Influence of the base temperature on the performance of tungsten under thermal and particle exposure
Nuclear materials and energy 12, 1348-1351 (2017) [10.1016/j.nme.2017.03.016]
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Mechanical properties of as-fabricated and 2300 °C annealed tungsten wire tested up to 600 °C
International journal of refractory metals & hard materials 66, 127 - 134 (2017) [10.1016/j.ijrmhm.2017.03.011]
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Erosion of installations in ports of a fusion reactor by hot fuel atoms
Nuclear materials and energy 12, 1298-1302 (2017) [10.1016/j.nme.2016.12.015]
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Modeling of localized impulsive injection of neutrals and plasma response
Plasma physics and controlled fusion 59(5), 055005 (2017) [10.1088/1361-6587/aa6219]
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Accelerated procedure to solve kinetic equation for neutral atoms in a hot plasma
Journal of physics / Conference Series 936(1), 012009 - (2017) [10.1088/1742-6596/936/1/012009]
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Baseline high heat flux and plasma facing materials for fusion
Nuclear fusion 57(9), 092006 - (2017) [10.1088/1741-4326/aa6b60]
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Erratum to: The 2016 Thermal Spray Roadmap
Journal of thermal spray technology 26(5), 985 - 986 (2017) [10.1007/s11666-017-0560-7]
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Ageing of structural materials in tokamaks: TEXTOR liner study
Physica scripta T170, 014053 (2017) [10.1088/1402-4896/aa8bee]
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Development and analyses of self-passivating tungsten alloys for DEMO accidental conditions
Fusion engineering and design 124, 183-186 (2017) [10.1016/j.fusengdes.2017.03.072]
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ITER core CXRS diagnostic: Assessment of different optical designs with respect to neutronics criteria
Fusion engineering and design 123, 927-931 (2017) [10.1016/j.fusengdes.2017.03.061]
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The DEMO wall load challenge
Nuclear fusion 57(4), 046002 - (2017) [10.1088/1741-4326/aa4fb4]
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The physics and technology basis entering European system code studies for DEMO
Nuclear fusion 57(1), 016011 (2017) [10.1088/0029-5515/57/1/016011]
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Control of particle and power exhaust in pellet fuelled ITER DT scenarios employing integrated models
Nuclear fusion 57(7), 076020 - (2017) [10.1088/1741-4326/aa6ecc]
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Impact of the JET ITER-like wall on H-mode plasma fueling
Nuclear fusion 57(6), 066024 - (2017) [10.1088/1741-4326/aa69dd]
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Poloidal correlation reflectometry at W7-X: radial electric field and coherent fluctuations
Plasma physics and controlled fusion 59(10), 105002 - (2017) [10.1088/1361-6587/aa759b]
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Enhancing the performance of high-voltage LiCoMnO$_{4}$ spinel electrodes by fluorination
Journal of power sources 341, 122 - 129 (2017) [10.1016/j.jpowsour.2016.11.100]
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Material Properties and Their Influence on the Behaviour of Tungsten as Plasma Facing Material
Nuclear fusion 57(6), 066018 - (2017) [10.1088/1741-4326/aa6938]
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High Pulse Number Thermal Shock Tests on Tungsten With Steady State Particle Background
Physica scripta T170, 014066 - (2017) [10.1088/1402-4896/aa909e]
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Transient heat load challenges for plasma-facing materials during long-term operation
Nuclear materials and energy 12, 148-155 (2017) [10.1016/j.nme.2016.12.024]
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Major results from the first plasma campaign of the Wendelstein 7-X stellarator
Nuclear fusion 57(10), 102020 - (2017) [10.1088/1741-4326/aa770d]
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Limiter observations during W7-X first plasmas
Nuclear fusion 57(5), 056036 (2017) [10.1088/1741-4326/aa6609]
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Observation of internal transport barrier in ELMy H-mode plasmas on the EAST tokamak
Plasma physics and controlled fusion 59(8), 085003 - (2017) [10.1088/1361-6587/aa6f2a]
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Implementation of ferritic steel as in vessel wall: Lessons learnt and follow up
Fusion engineering and design 124, 297 - 301 (2017) [10.1016/j.fusengdes.2017.04.016]
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Runaway electron generation during disruptions in the J-TEXT tokamak
Nuclear fusion 57(4), 046001 - (2017) [10.1088/1741-4326/aa57d9]
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Microstructure, mechanical behaviour and fracture of pure tungsten wire after different heat treatments
International journal of refractory metals & hard materials 68, 29 - 40 (2017) [10.1016/j.ijrmhm.2017.06.001]
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A stepladder approach to a tokamak fusion power plant
Nuclear fusion 57(8), 086002 - (2017) [10.1088/1741-4326/aa739e]
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