| Physics basis for the first ITER tungsten divertor |
49 |
| European divertor target concepts for DEMO: Design rationales and high heat flux performance |
18 |
| Additive manufacturing of pure tungsten by means of selective laser beam melting with substrate preheating temperatures up to 1000 degrees C |
14 |
| Recrystallization behavior of hot-rolled pure tungsten and its alloy plates during high-temperature annealing |
14 |
| Linear scaling DFT calculations for large tungsten systems using an optimized local basis |
11 |
| Hydrogen permeation barriers: Basic requirements, materials selection, deposition methods, and quality evaluation |
10 |
| Microstructure and mechanical properties of mechanically alloyed ODS copper alloy for fusion material application |
10 |
| Oxidation resistance of bulk plasma- facing tungsten alloys |
9 |
| Impact of ICRF on the scrape-off layer and on plasma wall interactions: From present experiments to fusion reactor |
8 |
| Stationarity of I-mode operation and I-mode divertor heat fluxes on the ASDEX Upgrade tokamak |
8 |
| WCrY smart alloys as advanced plasma-facing materials - Exposure to steady-state pure deuterium plasmas in PSI-2 |
8 |
| Improved pseudo-ductile behavior of powder metallurgical tungsten short fiber-reinforced tungsten (W-f/W) |
8 |
| Beryllium global erosion and deposition at JET-ILW simulated with ERO2.0 |
7 |
| Modelling of tungsten erosion and deposition in the divertor of JET-ILW in comparison to experimental findings |
7 |
| Comparison of the hydrogen permeation through fusion relevant steels and the influence of oxidized and rough surfaces |
7 |
| Investigation of deuterium trapping and release in the JET ITER-like wall divertor using TDS and TMAP |
7 |
| A growth/annealing equilibrium model for helium-induced nanostructure with application to ITER |
7 |
| Investigation of recombination front region in detached plasmas in a linear divertor plasma simulator |
7 |
| Influence of the presence of deuterium on displacement damage in tungsten |
7 |
| Real-time wall conditioning by controlled injection of boron and boron nitride powder in full tungsten wall ASDEX Upgrade |
6 |
| Experimental validation of a model for particle recycling and tungsten erosion during ELMs in the DIII-D divertor |
6 |
| Neutral pressure and separatrix density related models for seed impurity divertor radiation in ASDEX Upgrade |
6 |
| Temperature-dependent in-situ LEIS measurement of W surface enrichment by 250 eV D sputtering of EUROFER |
6 |
| Recent progress on the R&D of W-ZrC alloys for plasma facing components in fusion devices |
6 |
| Evidence of near-SOL tungsten accumulation using a far-SOL collector probe array and OEDGE modelling in the DIII-D metal rings L-mode discharges |
5 |
| Deposition of impurity metals during campaigns with the JET ITER-like Wall |
5 |
| Growth process of nano-tendril bundles with sputtered tungsten |
5 |
| Structural impact of creep in tungsten monoblock divertor target at 20 MW/m(2) |
5 |
| The effect of divertor closure on detachment onset in DIII-D |
5 |
| Comparing N versus Ne as divertor radiators in ASDEX-upgrade and ITER |
5 |
| The effect of beryllium oxide on retention in JET ITER-like wall tiles |
5 |
| Tritium retention characteristics in dust particles in JET with ITER-like wall |
5 |
| Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors |
5 |
| Nano-sized prismatic vacancy dislocation loops and vacancy clusters in tungsten |
5 |
| The effect of neutrals in the new SAS divertor at DIII-D as modelled by SOLPS |
5 |
| MEMOS 3D modelling of ELM-induced transient melt damage on an inclined tungsten surface in the ASDEX Upgrade outer divertor |
5 |
| Ion irradiation effects on FeCrAl-ODS ferritic steel |
5 |
| Depth resolved analysis of hydrogen in W7-X graphite components using laser-induced ablation-quadrupole mass spectrometry (LIA-QMS) |
5 |
| Detection by LIBS of the deuterium retained in the FTU toroidal limiter |
5 |
| Processing of complex near-net-shaped tungsten parts by PIM |
5 |
| In-situ fabrication of yttria dispersed copper alloys through MA-HIP process |
5 |
| Wall conditioning throughout the first carbon divertor campaign on Wendelstein 7-X |
5 |
| High pulse number thermal shock testing of tungsten alloys produced by powder injection molding |
5 |
| Metallic impurity sources behavior during ICRH in EAST |
4 |
| Fast camera imaging of plasmas in Alcator C-Mod and W7-X |
4 |
| Numerical simulation by finite element modelling of diffusion and transient hydrogen trapping processes in plasma facing components |
4 |
| Micro-structured tungsten: an advanced plasma-facing material |
4 |
| Real time wall conditioning with lithium powder injection in long pulse H-mode plasmas in EAST with tungsten divertor |
4 |
| Investigation of deuterium trapping and release in the JET divertor during the third ILW campaign using TDS |
4 |
| Identification of BeO and BeOxDy in melted zones of the JET Be limiter tiles: Raman study using comparison with laboratory samples |
4 |
