| Progress of the CFETR design |
40 |
| Overview of first Wendelstein 7-X high-performance operation |
39 |
| The IFMIF-DONES project: preliminary engineering design |
20 |
| Physics of runaway electrons in tokamaks |
19 |
| High temperature superconductors for fusion magnets |
17 |
| High-power gyrotrons for electron cyclotron heating and current drive |
17 |
| Overview of the DEMO staged design approach in Europe |
17 |
| First divertor physics studies in Wendelstein 7-X |
16 |
| Recent advances in EAST physics experiments in support of steady-state operation for ITER and CFETR |
16 |
| The European approach to the fusion-like neutron source: the IFMIF-DONES project |
16 |
| Experimental conditions to suppress edge localised modes by magnetic perturbations in the ASDEX Upgrade tokamak |
15 |
| Gyrokinetic analysis and simulation of pedestals to identify the culprits for energy losses using 'fingerprints' |
14 |
| Toroidal Alfven eigenmode triggered by trapped anisotropic energetic particles in a toroidal resistive plasma with free boundary |
14 |
| Overview of the JET preparation for deuterium-tritium operation with the ITER like-wall |
14 |
| Results from an improved flowing liquid lithium limiter with increased flow uniformity in high power plasmas in EAST |
14 |
| Dissipation of post-disruption runaway electron plateaus by shattered pellet injection in DIII-D |
13 |
| Fusion neutron production with deuterium neutral beam injection and enhancement of energetic-particle physics study in the large helical device |
12 |
| On the role of filaments in perpendicular heat transport at the scrape-off layer |
12 |
| Effect of the relative shift between the electron density and temperature pedestal position on the pedestal stability in JET-ILW and comparison with JET-C |
12 |
| High-resolution heat flux width measurements at reactor-level magnetic fields and observation of a unified width scaling across confinement regimes in the Alcator C-Mod tokamak |
12 |
| Compact fusion energy based on the spherical tokamak |
12 |
| First experimental tests of a new small angle slot divertor on DIII-D |
11 |
| Effects of divertor geometry on H-mode pedestal structure in attached and detached plasmas in the DIII-D tokamak |
11 |
| Progress of the JT-60SA project |
11 |
| A 3D dynamic model to assess the impacts of low-mode asymmetry, aneurysms and mix-induced radiative loss on capsule performance across inertial confinement fusion platforms |
11 |
| Advances in plasma-wall interaction control for H-mode operation over 100 s with ITER-like tungsten divertor on EAST |
11 |
| Integrated operation of steady-state long-pulse H-mode in Experimental Advanced Superconducting Tokamak |
11 |
| Diamagnetic energy measurement during the first operational phase at the Wendelstein 7-X stellarator |
11 |
| The effect of plasma shape and neutral beam mix on the rotation threshold for RMP-ELM suppression |
11 |
| Physics research on the TCV tokamak facility: from conventional to alternative scenarios and beyond |
11 |
| Overview of the recent experimental research on the J-TEXT tokamak |
11 |
| Machine learning for disruption warnings on Alcator C-Mod, DIII-D, and EAST |
11 |
| Motion of W and He atoms during formation of W fuzz |
10 |
| Access to pedestal pressure relevant to burning plasmas on the high magnetic field tokamak Alcator C-Mod |
10 |
| Beryllium melting and erosion on the upper dump plates in JET during three ITER-like wall campaigns |
10 |
| A multi-scale model for stresses, strains and swelling of reactor components under irradiation |
10 |
| Application of Gaussian process regression to plasma turbulent transport model validation via integrated modelling |
10 |
| Electron cyclotron power management for control of neoclassical tearing modes in the ITER baseline scenario |
10 |
| Erosion, screening, and migration of tungsten in the JET divertor |
10 |
| Properties of a new quasi-axisymmetric configuration |
10 |
| Optimisation of stellarator equilibria with ROSE |
9 |
| Simulations of tokamak boundary plasma turbulence transport in setting the divertor heat flux width |
9 |
| Electromagnetic turbulence suppression by energetic particle driven modes |
9 |
| Metis: a fast integrated tokamak modelling tool for scenario design |
9 |
| Retarded recrystallization of helium-exposed tungsten |
9 |
| Formation of hot, stable, long-lived field-reversed configuration plasmas on the C-2W device |
9 |
| New method to design stellarator coils without the winding surface |
9 |
| Experimental identification of nonlinear coupling between (intermediate, small)-scale microturbulence and an MHD mode in the core of a superconducting tokamak |
9 |
| Prediction of divertor heat flux width for ITER using BOUT plus plus transport and turbulence module |
9 |
| First principles and integrated modelling achievements towards trustful fusion power predictions for JET and ITER |
9 |
