ELM-wall interaction on JET and ITER

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Fusion plasma regimes with a strongly radiating magnetic 𝑋 point are promising candidates to tackle the outstanding power exhaust challenge in reactor-scale devices. In this Letter, we report on a new type of 𝑋-point radiator, the XPTR (𝑋-point target radi ...

The density limit in strongly-shaped negative triangularity (NT) discharges is studied experimentally in the DIII-D tokamak. Record-high Greenwald fractions f G are obtained, using gas puff injection only, with values up to near 2, where f G is defined as ...

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The design point that had been chosen for EU DEMO in 2016 is reviewed here and a modification is proposed with a lower aspect ratio. Previously the same aspect ratio, A, was chosen for EU DEMO as in major tokamak experiments including ITER (A = 3.1), and, ...

Negative triangularity (NT) scenarios in TCV have been compared to positive triangularity (PT) scenarios using the same plasma shapes foreseen for divertor tokamak test tokamak operations. The experiments provided a NT/PT L-mode pair and a PT H-mode with d ...

Plasma turbulence plays a fundamental role in determining the performances of magnetic confinement fusion devices, such as tokamaks. Advances in computer science, combined with the development of efficient physical models, have significantly improved our u ...

Under the auspices of EUROfusion, the ITER baseline (IBL) scenario has been jointly investigated on AUG and TCV in the past years and this paper reports on the developments on TCV. It is found that the performance of TCV IBL is mainly limited by (neoclassi ...

Plasmas with negative triangularity (NT) shape have been recently shown to be able to achieve H-mode levels of confinement in L-mode, avoiding detrimental edge localised modes. Therefore, this plasma geometry is now studied as a possible viable option for ...

The heat flux mitigation during the thermal quench (TQ) by the shattered pellet injection (SPI) is one of the major elements of disruption mitigation strategy for ITER. It's efficiency greatly depends on the SPI and the target plasma parameters, and is ult ...

The magnet feeders are part of the critical systems of a fusion reactor since they represent the interface between the in-cryostat components at 4.5 K and the room-temperature cryogenic plant and power supply. The European DEMO tokamak foresees 16 toroidal ...

In recent years a strong effort has been made to investigate disruption avoidance schemes in order to aid the development of integrated operational scenarios for ITER. Within the EUROfusion programme the disruptive H-mode density limit (HDL) has been studi ...

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The effects of different working gases on the transition from linear ohmic confinement (LOC) regime to saturated ohmic confinement (SOC) regime and its relation to the intrinsic toroidal rotation reversal phenomenon were explored in the TCV tokamak. The en ...

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A discharge with electron temperature up to 14 keV has been achieved in EAST. Analysis of the electron cyclotron current drive (ECCD) efficiency at high electron temperature under EAST parameters is presented using C3PO/LUKE code. Simulation results show t ...

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The overall performance of fusion devices, such as tokamaks, is strongly correlated to the phenomena that occur in the boundary region, the outer plasma region that faces the wall of the device. The boundary plays a crucial role in regulating the heat and ...

ELM-wall interaction on JET and ITER

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𝑋-Point Target Radiator Regime in Tokamak Divertor Plasmas

Operation above the Greenwald density limit in high performance DIII-D negative triangularity discharges

Global fluid simulations of plasma turbulence in stellarators

Gyrokinetic simulations of turbulence in magnetic fusion plasmas using a delta-f PIC scheme with evolving background

Re-design of EU DEMO with a low aspect ratio

Experiments and gyrokinetic simulations of TCV plasmas with negative triangularity in view of DTT operations

Nonlinear simulation of plasma turbulence using a gyrokinetic moment-based approach

Progress in the development of the ITER baseline scenario in TCV

First-principle based predictions of the effects of negative triangularity on DTT scenarios

Plasmoid drift and first wall heat deposition during ITER H-mode dual-SPIs in JOREK simulations

The magnet feeders for the European DEMO fusion reactor: Conceptual design and recent advances

Disruption avoidance and investigation of the H-Mode density limit in ASDEX Upgrade

Experimental study and interpretative modelling of the Power Exhaust in Configurations with Multiple X-Points in TCV

Study of correlations between LOC/SOC transition, intrinsic toroidal rotation reversal and TEM/ITG bifurcation with different working gases in TCV

Essay: Overcoming the Obstacles to a Magnetic Fusion Power Plant

Present design of the Steering Mirror Assembly (SMA) for ITER ECHUL

Optimization of X-mode electron cyclotron current drive in high-electron-temperature plasma in the EAST tokamak

The role of plasma-atom and molecule interactions on power & particle balance during detachment on the MAST Upgrade Super-X divertor

Modelling of nonneutral plasmas trapped by electric and magnetic fields relevant to gyrotron electron guns

A Gyrokinetic Moment Model of the Plasma Boundary in Fusion Devices