Publications 2023
Articles in refereed journals 2023
Global SOLPS-ITER and ERO2.0 coupling in a linear device for the study of plasma–wall interaction in helium plasma
Nuclear fusion 63(2), 026020 - (2023) [10.1088/1741-4326/acacaf]
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Recent progress of plasma exhaust concepts and divertor designs for tokamak DEMO reactors
Nuclear materials and energy 35, 101446 - (2023) [10.1016/j.nme.2023.101446]
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Optical properties and corrosion resistance of Ti2AlC, Ti3AlC2, and Cr2AlC as candidates for concentrated solar power receivers
Solar energy materials & solar cells 259, 112433 - (2023) [10.1016/j.solmat.2023.112433]
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Remote infrared view of JET divertor compatible with D-T operations
Plasma physics and controlled fusion 65(9), 094002 (2023) [10.1088/1361-6587/ace6d3]
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Remote wide angle view broad wavelength viewing system compatible with D-T operations in JET
Plasma physics and controlled fusion 65(6), 064005 - (2023) [10.1088/1361-6587/accecc]
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The X-Point radiating regime at ASDEX Upgrade and TCV
Nuclear materials and energy 34, 101376 - (2023) [10.1016/j.nme.2023.101376]
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Numerical error analysis of SOLPS-ITER simulations of EAST
Nuclear fusion 63(1), 016005 - (2023) [10.1088/1741-4326/aca0ab]
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Triple Langmuir probe calibration in TOMAS ECRH plasma
AIP Advances 13(5), 055125 (2023) [10.1063/5.0146388]
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W/Fe co-sputtered layers for tungsten to steel joints
Nuclear materials and energy 35, 101421 - (2023) [10.1016/j.nme.2023.101421]
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The ductile-brittle transition behaviors of W/Ta multilayer composites
Journal of alloys and compounds 946, 169377 - (2023) [10.1016/j.jallcom.2023.169377]
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Data processing and visualization tool for atomic and molecular data for collisional radiative models
The European physical journal / D 77(7), 139 (2023) [10.1140/epjd/s10053-023-00722-5]
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Evolution of Tungsten Fiber‐Reinforced Tungsten‐Remarks on Production and Joining
Advanced engineering materials 25(19), 2300569 (2023) [10.1002/adem.202300569]
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Testing of ITER-grade plasma facing units in the WEST tokamak: Progress in understanding heat loading and damage mechanisms
Nuclear materials and energy 37, 101546 - (2023) [10.1016/j.nme.2023.101546]
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Plasma exposure of a pre-damaged ITER-like plasma facing unit in the WEST tokamak: in-situ and post-mortem measurements
Nuclear materials and energy 34, 101366 - (2023) [10.1016/j.nme.2023.101366]
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Towards fast surrogate models for interpolation of tokamak edge plasmas
Nuclear materials and energy 34, 101396 - (2023) [10.1016/j.nme.2023.101396]
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First 3D modelling of tungsten erosion and migration in WEST discharges adopting a toroidally non-symmetric wall geometry
Nuclear materials and energy 34, 101340 - (2023) [10.1016/j.nme.2022.101340]
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Overview of plasma-tungsten surfaces interactions on the divertor test sector in WEST during the C3 and C4 campaigns
Nuclear materials and energy 34, 101399 - (2023) [10.1016/j.nme.2023.101399]
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Benchmarking by high heat flux testing of W-steel joining technologies
Nuclear materials and energy 37, 101508 - (2023) [10.1016/j.nme.2023.101508]
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Divertor power load investigations with deuterium and tritium in type-I ELMy H-mode plasmas in JET with the ITER-like wall
Nuclear fusion 63(11), 112013 - (2023) [10.1088/1741-4326/acddf8]
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Tungsten based divertor development for Wendelstein 7-X
Nuclear materials and energy 37, 101506 - (2023) [10.1016/j.nme.2023.101506]
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Erosion and redeposition pattern on the W7-X graphite test divertor unit tile
Fusion engineering and design 191, 113589 - (2023) [10.1016/j.fusengdes.2023.113589]
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Bubble Formation in ITER-Grade Tungsten after Exposure to Stationary D/He Plasma and ELM-like Thermal Shocks
Journal of nuclear engineering 4(1), 204 - 212 (2023) [10.3390/jne4010016]
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Processing and properties of sintered W/steel-composites for the first wall of future fusion reactor
Journal of nuclear engineering 4(1), 177-192 (2023) [10.3390/jne4010014]
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High heat flux testing of graded W-steel joining concepts for the first wall
Energies 16(9), 3664 (2023) [10.3390/en16093664]
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Determination of mechanical properties of tungsten/steel composites using image based microstructure modelling
Nuclear materials and energy 36, 101496 - (2023) [10.1016/j.nme.2023.101496]
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Early-stage structure and evolution mechanism of hydrogen supersaturated surface layers on tungsten under low-energy plasma exposure
Acta materialia 256, 119137 - (2023) [10.1016/j.actamat.2023.119137]
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Review of Recent Progress in Plasma-Facing Material Joints and Composites in the FRONTIER U.S.-Japan Collaboration
Fusion science and technology 79(6), 662 - 670 (2023) [10.1080/15361055.2023.2176687]
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Advances, Challenges, and Future Perspectives of Microwave Reflectometry for Plasma Position and Shape Control on Future Nuclear Fusion Devices
Sensors 23(8), 3926 - (2023) [10.3390/s23083926]
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Characterisation of divertor detachment onset in JET-ILW hydrogen, deuterium, tritium and deuterium–tritium low-confinement mode plasmas
Nuclear materials and energy 34, 101345 - (2023) [10.1016/j.nme.2022.101345]
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Atomic collisional data for neutral beam modeling in fusion plasmas
Nuclear fusion 63(12), 125001 (2023) [10.1088/1741-4326/acf5da]
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High heat flux performance assessment of ITER enhanced heat flux first wall technology after neutron irradiation
Fusion engineering and design 186, 113338 - (2023) [10.1016/j.fusengdes.2022.113338]
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Hydrogen isotope permeation through interfaces and permeability of tungsten layers
Nuclear materials and energy 37, 101518 - (2023) [10.1016/j.nme.2023.101518]
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Design of new resonant magnetic perturbation coils on the J-TEXT tokamak
Plasma science & technology 25(11), 115601 - (2023) [10.1088/2058-6272/acd997]
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An application of the shortest path algorithm for the identification of weak MHD mode
Plasma science & technology 25(8), 085101 - (2023) [10.1088/2058-6272/acc055]
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Initial study on thermal stability of cold spray tantalum coating irradiated with deuterium for fusion applications
Physica scripta 98(11), 115611 - (2023) [10.1088/1402-4896/ad0098]
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Thermal fatigue response of W-EUROFER brazed joints by the application of High Heat Flux loads
Journal of materials processing technology 319, 118056 - (2023) [10.1016/j.jmatprotec.2023.118056]
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ICRH operations and experiments during the JET-ILW tritium and DTE2 campaigns
24TH TOPICAL CONFERENCE ON RADIO-FREQUENCY POWER IN PLASMAS, AnnapolisAnnapolis, USA,
AIP conference proceedings 2984, 030003 (2023) [10.1063/5.0162645]
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Innovative Tungsten Coatings for an Application in Modern and Future Fusion Devices
Metals 13(3), 531 - (2023) [10.3390/met13030531]
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Erosion estimates for the divertor and main wall components from STEP
Nuclear fusion 63(12), 126055 - (2023) [10.1088/1741-4326/ad067d]
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Supervised learning approaches to modeling pedestal density
Plasma physics and controlled fusion 65(4), 045003 - (2023) [10.1088/1361-6587/acb3f7]
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Developing deep learning algorithms for inferring upstream separatrix density at JET
Nuclear materials and energy 34, 101347 - (2023) [10.1016/j.nme.2022.101347]
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Comparison of ion cyclotron wall conditioning discharges in hydrogen and helium in JET
Nuclear materials and energy 37, 101521 - (2023) [10.1016/j.nme.2023.101521]
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Measurement of hydrogen plasma parameters of the combined ECR+RF discharge in the TOMAS facility
24TH TOPICAL CONFERENCE ON RADIO-FREQUENCY POWER IN PLASMAS, AnnapolisAnnapolis, USA,
AIP conference proceedings 2984, 110001 (2023) [10.1063/5.0162408]
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Overview of TOMAS plasma diagnostics
Journal of Instrumentation 18(02), C02034 - (2023) [10.1088/1748-0221/18/02/C02034]
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First feedback-controlled divertor detachment in W7-X: Experience from TDU operation and prospects for operation with actively cooled divertor
Nuclear materials and energy 34, 101363 - (2023) [10.1016/j.nme.2023.101363]
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Bulk Tungsten Fiber-Reinforced Tungsten (Wf/W) Composites Using Yarn-Based Textile Preforms
Journal of nuclear engineering 4(2), 375 - 390 (2023) [10.3390/jne4020027]
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Application of a hyperspectral camera for in situ plasma–material interaction studies at the linear plasma device PSI-2
Review of scientific instruments 94(8), 083501 (2023) [10.1063/5.0155722]
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Effect of edge ion temperature on the divertor tungsten sputtering in WEST
Nuclear fusion 63(2), 026019 - (2023) [10.1088/1741-4326/acacb0]
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Edge turbulence transport during ELM suppression with n = 4 resonant magnetic perturbation on EAST
Nuclear fusion 63(4), 042003 - (2023) [10.1088/1741-4326/acbce5]
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Parameter dependencies of the separatrix density in low triangularity L-mode and H-mode JET-ILW plasmas
Nuclear fusion 63(3), 036019 - (2023) [10.1088/1741-4326/aca9de]
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Neutronics Simulations for DEMO Diagnostics
Sensors 23(11), 5104 - (2023) [10.3390/s23115104]
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A diagnostics slim cassette for reflectometry measurements in DEMO: Design and simulation studies
Fusion engineering and design 190, 113512 - (2023) [10.1016/j.fusengdes.2023.113512]
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Microstructures and mechanical properties of α-Al 2 O 3W and MWCNTs hybrid reinforced laminated Cu matrix composites
Composite interfaces 30(4), 341-360 (-) [10.1080/09276440.2022.2111800]
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Integrated control of edge localized modes and divertor flux using mixed toroidal harmonic resonant magnetic perturbations in EAST
Physics of plasmas 30(12), 122507 (2023) [10.1063/5.0170003]
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Electrophoretic deposition prepared yttria as interface of tungsten fiber reinforced tungsten composites
Nuclear materials and energy 36, 101487 - (2023) [10.1016/j.nme.2023.101487]
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Tritium removal from JET-ILW after T and D–T experimental campaigns
Nuclear fusion 63(11), 112014 - (2023) [10.1088/1741-4326/acf0d4]
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Studies on EU-DEMO 3D coils requirements and conceptual design for error field correction and plasma control
Fusion engineering and design 196, 114010 - (2023) [10.1016/j.fusengdes.2023.114010]
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Achievement of ion temperatures in excess of 100 million degrees Kelvin in the compact high-field spherical tokamak ST40
Nuclear fusion 63(5), 054002 - (2023) [10.1088/1741-4326/acbec8]
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Hydrogen isotope analysis in W-tiles using fs-LIBS
Scientific reports 13(1), 2285 (2023) [10.1038/s41598-023-29138-2]
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Performance of tungsten plasma facing components in the stellarator experiment W7-X: Recent results from the first OP2 campaign
Nuclear materials and energy 37, 101514 - (2023) [10.1016/j.nme.2023.101514]
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Multiphysics Modeling of Impurity Transport for FNSF Startup Scenario with ERO2.0
Fusion science and technology 79(3), 213-221 (2023) [10.1080/15361055.2022.2148840]
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Material and component developments for the DEMO divertor using fibre reinforcement and additive manufacturing
Materials Research Express 10(11), 116516 - (2023) [10.1088/2053-1591/ad0c7c]
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Thermomechanical analysis of a multi-reflectometer system for DEMO
Fusion engineering and design 190, 113530 - (2023) [10.1016/j.fusengdes.2023.113530]
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Physics design, construction and commissioning of the ICRH system for the stellarator Wendelstein 7-X
Fusion engineering and design 192, 113627 - (2023) [10.1016/j.fusengdes.2023.113627]
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Fast dynamic 1D simulation of divertor plasmas with neural PDE surrogates
Nuclear fusion 63(12), 126012 - (2023) [10.1088/1741-4326/acf70d]
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Dependence of tungsten crack behaviors on heat source parameters under transient heat flow
Materials science & engineering / A 874, 145079 - (2023) [10.1016/j.msea.2023.145079]
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FIB line marking as a tool for local erosion/deposition/fuzz formation measurements in ASDEX Upgrade during the He campaign
Nuclear materials and energy 37, 101539 - (2023) [10.1016/j.nme.2023.101539]
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Space-resolved line shape model for sputtered atoms of finite-size targets
Physica scripta 98(11), 115603 - (2023) [10.1088/1402-4896/acfe4a]
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Microstructure and mechanical properties of Wf/W composites influenced by Y2O3 coating
International journal of refractory metals & hard materials 115, 106322 - (2023) [10.1016/j.ijrmhm.2023.106322]
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Overview of interpretive modelling of fusion performance in JET DTE2 discharges with TRANSP
Nuclear fusion 63(12), 126058 (2023) [10.1088/1741-4326/ad0310]
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The broadening of SOL profiles in JET tritium plasma and its impact on machine operation
Nuclear fusion 63(1), 016021 - (2023) [10.1088/1741-4326/aca48f]
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Effect of neutron irradiation on tensile properties of advanced Cu-based alloys and composites developed for fusion applications
Journal of nuclear materials 584, 154587 - (2023) [10.1016/j.jnucmat.2023.154587]
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Segregation-enhanced grain boundary embrittlement of recrystallised tungsten evidenced by site-specific microcantilever fracture
Acta materialia 259, 119256 - (2023) [10.1016/j.actamat.2023.119256]
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SOLPS-ITER drift modeling of neon impurity seeded plasmas in EAST with favorable and unfavorable toroidal magnetic field direction
Plasma science & technology 25(11), 115102 - (2023) [10.1088/2058-6272/ace026]
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Invariant manifold growth formula in cylindrical coordinates and its application for magnetically confined fusion
Plasma science & technology 25(9), 095105 - (2023) [10.1088/2058-6272/accbf5]
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Testing of the tungsten pin dump prototype at the JUDITH 2 testing facility
Journal of Instrumentation 18(04), T04001 - (2023) [10.1088/1748-0221/18/04/T04001]
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Investigation of a low frequency coherent mode in Wendelstein 7-X with island divertor
Nuclear fusion 63(12), 126050 - (2023) [10.1088/1741-4326/ad0415]
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Modeling of plasma beta effects on the island divertor transport in the standard configuration of W7-X
Nuclear fusion 63(6), 066005 - (2023) [10.1088/1741-4326/acc7b8]
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Fuel desorption from JET-ILW materials: assessment of analytical approach and identification of sources of uncertainty and discrepancy
Nuclear fusion 63(9), 096010 - (2023) [10.1088/1741-4326/ace2d2]
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