Publikationen 2021
Beiträge in referierten Zeitschriften 2021
ERO2.0 modelling of nanoscale surface morphology evolution
Nuclear fusion 61(6), 066039 - (2021) [10.1088/1741-4326/abfcde]
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Self-passivating smart tungsten alloys for DEMO: a progress in joining and upscale for a first wall mockup
Tungsten 3(1), 101–115 (2021) [10.1007/s42864-021-00079-5]
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Summary of the IAEA technical meeting on plasma disruptions and their mitigation
Nuclear fusion 61(7), 077001 - (2021) [10.1088/1741-4326/abfe76]
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Design and integration studies of a diagnostics slim cassette concept for DEMO
Nuclear fusion 61(11), 116046 - (2021) [10.1088/1741-4326/ac24d3]
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Deuterium and helium outgassing following plasma discharges in WEST: Delayed D outgassing during D-to-He changeover experiments studied with threshold ionization mass spectrometry
Nuclear materials and energy 26, 100885 - (2021) [10.1016/j.nme.2020.100885]
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Towards assessment of plasma edge transport in Neon seeded plasmas in disconnected double null configuration in EAST with SOLPS-ITER
Nuclear materials and energy 26, 100926 - (2021) [10.1016/j.nme.2021.100926]
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Divertor power load predictions based on machine learning
Nuclear fusion 61(4), 046023 - (2021) [10.1088/1741-4326/abdb94]
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Design improvements, assembly and testing of the ICRH antenna for W7-X
Fusion engineering and design 166, 112205 - (2021) [10.1016/j.fusengdes.2020.112205]
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Microstructures and mechanical properties of nano-C and in situ Al2O3 reinforced aluminium matrix composites processed by equal-channel angular pressing
Journal of alloys and compounds 876, 160159 - (2021) [10.1016/j.jallcom.2021.160159]
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Phase transformation and strengthening mechanisms of nanostructured high-entropy alloys
Nanotechnology reviews 10(1), 1116 - 1139 (2021) [10.1515/ntrev-2021-0071]
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The impact of ELM mitigation on tungsten source in the EAST divertor
Nuclear fusion 61(4), 046046 - (2021) [10.1088/1741-4326/abe697]
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Three-dimensional first principles simulation of a hydrogen discharge
Plasma physics and controlled fusion 63(4), 045012 - (2021) [10.1088/1361-6587/abdd75]
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TECXY simulations of Ne seeding in JET high power scenarios
Nuclear materials and energy 27, 100962 - (2021) [10.1016/j.nme.2021.100962]
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Interpretative modeling of impurity transport and tungsten sources in WEST boundary plasma
Nuclear fusion 61(12), 126015 - (2021) [10.1088/1741-4326/ac2439]
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Tungsten fiber reinforced tungsten (Wf/W) using yarn based textile preforms
Physica scripta 96(12), 124063 - (2021) [10.1088/1402-4896/ac37cf]
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Sustained W-melting experiments on actively cooled ITER-like plasma facing unit in WEST
Physica scripta 96(12), 124057 - (2021) [10.1088/1402-4896/ac326a]
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Data on erosion and hydrogen fuel retention in Beryllium plasma-facing materials
Nuclear materials and energy 27, 100994 - (2021) [10.1016/j.nme.2021.100994]
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Plasma edge simulations including realistic wall geometry with SOLPS-ITER
Nuclear materials and energy 27, 100999 - (2021) [10.1016/j.nme.2021.100999]
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Plasma-wall interaction studies in W7-X: main results from the recent divertor operations
Physica scripta 96(12), 124059 - (2021) [10.1088/1402-4896/ac35c0]
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Modelling of tungsten contamination and screening in WEST plasma discharges
Nuclear fusion 61(10), 106019 - (2021) [10.1088/1741-4326/ac2026]
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Additive manufacturing of high density pure tungsten by electron beam melting
Nuclear materials and energy 28, 101046 - (2021) [10.1016/j.nme.2021.101046]
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Effectiveness of local methane and hydrogen injection into the scrape-off layer of W7-X by means of the multi-purpose manipulator
Fusion engineering and design 173, 112786 - (2021) [10.1016/j.fusengdes.2021.112786]
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The impact of surface morphology on the erosion of metallic surfaces – Modelling with the 3D Monte-Carlo code ERO2.0
Nuclear materials and energy 27, 100987 - (2021) [10.1016/j.nme.2021.100987]
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Wendelstein 7-X on the path to long-pulse high-performance operation
Fusion engineering and design 167, 112381 - (2021) [10.1016/j.fusengdes.2021.112381]
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Hydrogen isotope permeation through yttria coatings on Eurofer in the diffusion limited regime
International journal of hydrogen energy 46(24), 13142 - 13149 (2021) [10.1016/j.ijhydene.2021.01.072]
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Monitoring Removal of W Layer from Ag Substrate Using Balmer-α Emission of Backscattered Hydrogen Atoms in Low Density Gas Discharge. Acta Physica Polonica A 138, 643 (2020), ERRATUM
Acta physica Polonica / A 139(2), 170 - 171 (2021) [10.12693/APhysPolA.139.170]
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Measurements of the energy distribution of W atoms sputtered by low energy Ar ions using high-resolution Doppler spectroscopy
Plasma physics and controlled fusion 63(1), 015008 (2021) [10.1088/1361-6587/abc519]
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Impact of magnetic islands on plasma flow and turbulence in W7-X
Nuclear fusion 61, 096011 (2021) [10.1088/1741-4326/ac146f]
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Cross diagnostics measurements of heat load profiles on the lower tungsten divertor of WEST in L-mode experiments
Nuclear materials and energy 27, 100961 - (2021) [10.1016/j.nme.2021.100961]
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Advanced design of the ITER core CXRS shutter and integration into the diagnostic shield module of the Upper Port Plug No. 3
Fusion engineering and design 168, 112391 - (2021) [10.1016/j.fusengdes.2021.112391]
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Synergistic and separate effects of plasma and transient heat loads on the microstructure and physical properties of ITER-grade tungsten
Physica scripta 96(12), 124052 - (2021) [10.1088/1402-4896/ac326c]
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Manufacturing of W-steel joint using plasma sprayed graded W/steel-interlayer with current assisted diffusion bonding
Fusion engineering and design 172, 112896 - (2021) [10.1016/j.fusengdes.2021.112896]
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Divertor power loads and scrape off layer width in the large aspect ratio full tungsten tokamak WEST
Nuclear fusion 61(9), 096027 - (2021) [10.1088/1741-4326/ac1803]
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Interlayer properties of tungsten fibre-reinforced composites and their determination by different methods
Nuclear materials and energy 28, 101060 - (2021) [10.1016/j.nme.2021.101060]
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The upgraded TOMAS device: A toroidal plasma facility for wall conditioning, plasma production, and plasma–surface interaction studies
Review of scientific instruments 92(2), 023506 - (2021) [10.1063/5.0033229]
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Gross and net erosion balance of plasma-facing materials in full-W tokamaks
Nuclear fusion 61(11), 116006 - (2021) [10.1088/1741-4326/ac22d2]
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Application of the elliptic approximation model for the edge turbulence rotation measurement via the poloidal correlation reflectometer in Wendelstein 7-X
Nuclear fusion 61(6), 066029 - (2021) [10.1088/1741-4326/abfb15]
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Comparison of a collisional-radiative fluid model of H2 in UEDGE to the kinetic neutral code EIRENE
Nuclear materials and energy 27, 100982 - (2021) [10.1016/j.nme.2021.100982]
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Application of spatially hybrid fluid–kinetic neutral model on JET L-mode plasmas
Nuclear materials and energy 27, 100969 - (2021) [10.1016/j.nme.2021.100969]
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Progress on MATEO probe heads and observation system
Fusion engineering and design 167, 112297 - (2021) [10.1016/j.fusengdes.2021.112297]
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Scaling of impurity fractions for divertor detachment in high-density high-power operation scenarios
Nuclear fusion 61(3), 036049 - (2021) [10.1088/1741-4326/abdded]
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Understanding tungsten erosion during inter/intra-ELM periods in He-dominated JET-ILW plasmas
Physica scripta 96(12), 124046 - (2021) [10.1088/1402-4896/ac2d85]
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Overview of the results from divertor experiments with attached and detached plasmas at Wendelstein 7-X and their implications for steady-state operation
Nuclear fusion 61(10), 106003 - (2021) [10.1088/1741-4326/ac1b68]
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Integrated ELM and divertor power flux control using RMPs with low input torque in EAST in support of the ITER research plan
Nuclear fusion 61(10), 106023 - (2021) [10.1088/1741-4326/ac21f9]
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In situ study of short-term retention of deuterium in tungsten during and after plasma exposure in PSI-2
Nuclear fusion 61(9), 096006 - (2021) [10.1088/1741-4326/ac112e]
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Deuterium retention in tungsten fiber-reinforced tungsten composites
Nuclear materials and energy 27, 100972 - (2021) [10.1016/j.nme.2021.100972]
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SOLPS-ITER drift modelling of JET Ne and N-seeded H-modes
Nuclear materials and energy 28, 101030 - (2021) [10.1016/j.nme.2021.101030]
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Smart alloys as armor material for DEMO: Overview of properties and joining to structural materials
Fusion engineering and design 166, 112272 - (2021) [10.1016/j.fusengdes.2021.112272]
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Derivation of an improved semi-empirical expression for the re-ionisation background in low energy ion scattering spectra
IOP SciNotes 2(3), 035206 - (2021) [10.1088/2633-1357/ac25e8]
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Two-modes model of the non-equilibrium plasma chemical dissociation of CO 2
Plasma sources science and technology 30(5), 055003 - (2021) [10.1088/1361-6595/abf368]
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Comparative analysis of the plasma parameters of ECR and combined ECR + RF discharges in the TOMAS plasma facility
Plasma physics and controlled fusion 63(12), 125023 - (2021) [10.1088/1361-6587/ac3471]
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Main design features of the Rh-based first mirror developed for the ITER CXRS core diagnostics
Fusion engineering and design 169, 112408 - (2021) [10.1016/j.fusengdes.2021.112408]
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Standards for the Characterization of Endurance in Resistive Switching Devices
ACS nano 15(11), 17214 - 17231 (2021) [10.1021/acsnano.1c06980]
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Use of the Culham He model He II atomic data in JET EDGE2D-EIRENE simulations
Nuclear materials and energy 27, 101010 - (2021) [10.1016/j.nme.2021.101010]
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Modeling of SOL helical current filaments induced by biased electrode on J-TEXT
Plasma physics and controlled fusion 63(11), 115017 - (2021) [10.1088/1361-6587/ac2373]
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Advanced Self-Passivating Alloys for an Application under Extreme Conditions
Metals 11(8), 1255 - (2021) [10.3390/met11081255]
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Exploring the Interface of Skin‐Layered Titanium Fibers for Electrochemical Water Splitting
Advanced energy materials 11(8), 2002926 (2021) [10.1002/aenm.202002926]
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Constructing a Multifunctional Interface between Membrane and Porous Transport Layer for Water Electrolyzers
ACS applied materials & interfaces 13(14), 16182 - 16196 (2021) [10.1021/acsami.0c20690]
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The effect of bonding temperature on the bending behaviors and toughening mechanism of W/(Ti/Ta/Ti) multilayer composites prepared by field activated sintering technique
Materials characterization 172, 110875 - (2021) [10.1016/j.matchar.2021.110875]
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Application of a newly developed radial directional electron probe to the edge unidirectional electron current measurement in EAST
Nuclear materials and energy 29, 101080 - (2021) [10.1016/j.nme.2021.101080]
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Modelling and application of a new method to measure the non-thermal electron current in the edge of magnetically confined plasma
Nuclear fusion 61(12), 126004 - (2021) [10.1088/1741-4326/ac2aba]
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Nuclear analysis of the DEMO divertor survey visible high-resolution spectrometer
Fusion engineering and design 169, 112460 - (2021) [10.1016/j.fusengdes.2021.112460]
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Characterization of injection and confinement improvement through impurity induced profile modifications on the Wendelstein 7-X stellarator
Physics of plasmas 28(8), 082506 - (2021) [10.1063/5.0047274]
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Design of tungsten fiber-reinforced tungsten composites with porous matrix
Materials science and engineering / A 817, 141361 - (2021) [10.1016/j.msea.2021.141361]
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Short-term retention in metallic PFCs: modelling in view of mass spectrometry and LIBS
Physica scripta 96(12), 124079 - (2021) [10.1088/1402-4896/ac43d6]
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Impact of plasma-wall interaction and exhaust on the EU-DEMO design
Nuclear materials and energy 26, 100897 - (2021) [10.1016/j.nme.2020.100897]
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Erosion of tungsten marker layers in W7-X
Physica scripta 96(12), 124070 - (2021) [10.1088/1402-4896/ac3b68]
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Symmetries of 13C tracer deposition in EAST D and He plasmas investigated on the sub-mm to 100 mm scale by deuteron nuclear reaction analysis
Fusion engineering and design 166, 112292 - (2021) [10.1016/j.fusengdes.2021.112292]
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A New High-Throughput Focused MeV Ion-Beam Analysis Setup
Instruments 5(1), 10 - (2021) [10.3390/instruments5010010]
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Scaling of deuterium retention in < 3 MeV proton damaged Beryllium, Eurofer, and W-5Re in the range of 0.0003 to 6 DPA
Physica scripta 96, 124051 (2021) [10.1088/1402-4896/ac2efb]
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Characterization of neutral particle fluxes from ICWC and ECWC plasmas in the TOMAS facility
Physica scripta 96(12), 124025 - (2021) [10.1088/1402-4896/ac2494]
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Combined high fluence and high cycle number transient loading of ITER-like monoblocks in Magnum-PSI
Nuclear fusion 61(11), 116045 - (2021) [10.1088/1741-4326/ac25c2]
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Nuclear and thermal analysis of a multi-reflectometer system for DEMO
Fusion engineering and design 167, 112349 - (2021) [10.1016/j.fusengdes.2021.112349]
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Double pulse laser-induced breakdown spectroscopy for the analysis of plasma-facing components
Physica scripta 96(12), 124064 - (2021) [10.1088/1402-4896/ac379c]
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Analyses of deuterium retention in tungsten and graphite first wall materials by laser-induced ablation spectroscopy on EAST
Fusion engineering and design 162, 112108 - (2021) [10.1016/j.fusengdes.2020.112108]
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Hydrogen content in divertor baffle tiles in Wendelstein 7-X
Nuclear materials and energy 26, 100943 - (2021) [10.1016/j.nme.2021.100943]
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Advances in the physics and thermohydraulics of nuclear reactors
The European physical journal / Plus 136(8), 845 (2021) [10.1140/epjp/s13360-021-01391-2]
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Correction and verification of x-ray imaging crystal spectrometer analysis on Wendelstein 7-X through x-ray ray tracing
Review of scientific instruments 92(4), 043530 - (2021) [10.1063/5.0043513]
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Evidence of supercoolable nanoscale water clusters in an amorphous ionic liquid matrix
The journal of chemical physics 155(17), 174501 (2021) [10.1063/5.0066180]
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Yttria-Coated Tungsten Fibers for Use in Tungsten Fiber-Reinforced Composites: A Comparative Study on PVD vs. CVD Routes
Coatings 11(9), 1128 - (2021) [10.3390/coatings11091128]
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D retention and material defects probed using Raman microscopy in JET limiter samples and beryllium-based synthesized samples
Physica scripta 96(12), 124031 - (2021) [10.1088/1402-4896/ac267b]
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High heat flux testing of newly developed tungsten components for WEST
Fusion engineering and design 173, 112835 - (2021) [10.1016/j.fusengdes.2021.112835]
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Modeling and experimental validation of a W f /W-fabrication by chemical vapor deposition and infiltration
Nuclear materials and energy 28, 101048 (2021) [10.1016/j.nme.2021.101048]
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Improving the W Coating Uniformity by a COMSOL Model-Based CVD Parameter Study for Denser Wf/W Composites
Metals 11(7), 1089 - (2021) [10.3390/met11071089]
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Simultaneous irradiation and thermal effects on 16 MeV proton irradiated tungsten samples
Physica scripta 96(12), 124014 - (2021) [10.1088/1402-4896/ac1cf3]
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Determining Chemical Reaction Systems in Plasma-Assisted Conversion of Methane Using Genetic Algorithms
Plasma chemistry and plasma processing 41, 793–813 (2021) [10.1007/s11090-021-10159-6]
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Technology readiness assessment of materials for DEMO in-vessel applications
Journal of nuclear materials 550, 152906 - (2021) [10.1016/j.jnucmat.2021.152906]
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Fabrication routes for advanced first wall design alternatives
Nuclear fusion 61(11), 116067 - (2021) [10.1088/1741-4326/ac2523]
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Impact of materials technology on the breeding blanket design – Recent progress and case studies in materials technology
Fusion engineering and design 166, 112275 - (2021) [10.1016/j.fusengdes.2021.112275]
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Technological aspects in blanket design: Effects of micro-alloying and thermo-mechanical treatments of EUROFER97 type steels after neutron irradiation
Fusion engineering and design 168, 112645 - (2021) [10.1016/j.fusengdes.2021.112645]
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A sensitivity analysis of numerical predictions for beryllium erosion and migration in ITER
Nuclear materials and energy 26, 100904 - (2021) [10.1016/j.nme.2021.100904]
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Multi-machine SOLPS-ITER comparison of impurity seeded H-mode radiative divertor regimes with metal walls
Nuclear fusion 61(12), 126073 - (2021) [10.1088/1741-4326/ac3699]
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Zeeman-resolved TDLAS using metastable levels of Ar in the weakly magnetized plasma of the linear plasma device PSI-2
Journal of physics / D 54(39), 395001 - (2021) [10.1088/1361-6463/ac0fa9]
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Measurement performance assessment for the ITER CXRS Edge diagnostic system
Review of scientific instruments 92(5), 053517 - (2021) [10.1063/5.0042029]
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Simulation of Impurity Transport and Deposition in the Closed Helical Divertor in the Large Helical Device
Plasma and fusion research 16(0), 2403004 (2021) [10.1585/pfr.16.2403004]
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Interpretation of the hydrogen isotope effect on the density limit in JET-ILW L-mode plasmas using EDGE2D-EIRENE
Physica scripta 96(12), 124028 - (2021) [10.1088/1402-4896/ac267c]
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The role of edge plasma parameters in H-mode density limit on the JET-ILW
Nuclear fusion 61(6), 066009 - (2021) [10.1088/1741-4326/abf056]
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First demonstration of full ELM suppression in low input torque plasmas to support ITER research plan using n = 4 RMP in EAST
Nuclear fusion 61(10), 106037 - (2021) [10.1088/1741-4326/ac1a1d]
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Characteristics of Microstructure Evolution during FAST Joining of the Tungsten Foil Laminate
Metals 11(6), 886 - (2021) [10.3390/met11060886]
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Runaway electron generation and loss in EAST disruptions
Nuclear fusion 61(7), 076003 - (2021) [10.1088/1741-4326/abf62f]
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Impurity behaviour in JET-ILW plasmas fuelled with gas and/or with pellets: a comparative study with the transport code COREDIV
Nuclear fusion 61(6), 066027 - (2021) [10.1088/1741-4326/abf74c]
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Optimized design of a tungsten–copper functionally graded material monoblock for minimal von Mises stress meeting the material operational temperature window
Nuclear fusion 61(4), 046050 - (2021) [10.1088/1741-4326/abe7bb]
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Monitoring of tritium and impurities in the first wall of fusion devices using a LIBS based diagnostic
Nuclear fusion 61(12), 125001 - (2021) [10.1088/1741-4326/ac31d6]
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Deposition of 13C tracer and impurity elements on the divertor of Wendelstein 7-X
Physica scripta 96(12), 124023 - (2021) [10.1088/1402-4896/ac2381]
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Influence of the X-point location on edge plasma transport in the J-TEXT tokamak with a high-field-side single-null divertor
Plasma science & technology 23(12), 125103 - (2021) [10.1088/2058-6272/ac224a]
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Progress of Divertor Heat and Particle Flux Control in EAST for Advanced Steady-State Operation in the Last 10 Years
Journal of fusion energy 40(1), 3 (2021) [10.1007/s10894-021-00290-9]
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On grain growth and phase precipitation behaviors during W-Cr-Zr alloy densification using field-assisted sintering technology
International journal of refractory metals & hard materials 98, 105552 - (2021) [10.1016/j.ijrmhm.2021.105552]
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Application of 3D MHD equilibrium calculation to RMP experiments in the J-TEXT tokamak
Plasma science & technology 23(8), 085104 - (2021) [10.1088/2058-6272/ac0492]
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Effect of rhenium on defects evolution behavior in tungsten under irradiation
Nuclear fusion 61(3), 036037 - (2021) [10.1088/1741-4326/abd920]
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Analysis of HL-2A charge exchange spectra using parallel genetic algorithm
Fusion engineering and design 168, 112680 - (2021) [10.1016/j.fusengdes.2021.112680]
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An interpretive model for the double peaks of divertor tungsten erosion during type-I ELMs in EAST
Nuclear fusion 61(8), 086011 - (2021) [10.1088/1741-4326/ac086a]
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Effect of Ta addition on microstructures, mechanical and damping properties of Cu–Al–Mn–Ti alloy
Journal of materials research and technology 15, 3825 - 3835 (2021) [10.1016/j.jmrt.2021.10.031]
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Effects of alloying, heat treatment and nanoreinforcement on mechanical properties and damping performances of Cu–Al-based alloys: A review
Nanotechnology reviews 10(1), 1560 - 1591 (2021) [10.1515/ntrev-2021-0101]
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Influence of the applied pressure on the microstructure evolution of W-Cr-Y-Zr alloys during the FAST process
Fusion engineering and design 169, 112474 - (2021) [10.1016/j.fusengdes.2021.112474]
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Deuterium retention in MeV ion-irradiated beryllium
Journal of nuclear materials 555, 153139 - (2021) [10.1016/j.jnucmat.2021.153139]
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Plasma radiation behavior approaching high-radiation scenarios in W7-X
Nuclear fusion 61(12), 126002 - (2021) [10.1088/1741-4326/ac2b75]
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Effect of edge magnetic island on carbon screening in the J-TEXT tokamak
Plasma science & technology 23(12), 125101 - (2021) [10.1088/2058-6272/ac1dfc]
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Quantification of erosion pattern using picosecond-LIBS on a vertical divertor target element exposed in W7-X
Nuclear fusion 61(1), 016025 - (2021) [10.1088/1741-4326/abc408]
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Disruption prediction and model analysis using LightGBM on J-TEXT and HL-2A
Plasma physics and controlled fusion 63(7), 075008 - (2021) [10.1088/1361-6587/abfa74]
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