Benchmark of a self-consistent dynamic 1D divertor model DIV1D using the 2D SOLPS-ITER code

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The challenge of power exhaust of the high heat and particle fluxes foreseen for ITER and the forthcoming nuclear fusion reactors can be mitigated by operating in a detached divertor regime. This regime has been the object of three decades of studies, as i ...

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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, ...

A key challenge for the development of fusion reactors based on magnetic confinement, such as tokamaks and stellarators, is the control of the turbulent processes. The most prominent feature of turbulence in the Scrape-Off Layer (SOL), the volume between t ...

Rapid inter-discharge simulation and optimization using the RAPTOR code have allowed the development of a reliable and reproducible early heating strategy for an advanced tokamak (AT) scenario on ASDEX Upgrade. Solving for electron heat and current diffusi ...

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 effect of divertor closure and nitrogen seeding on the detachment process has been studied by performing 2D numerical simulations of tokamak a configuration variable (TCV) H-mode divertor scenarios with the SOLEDGE3X-EIRENE edge plasma transport code. ...

After the second Deuterium-Tritium Campaign (DTE2) in the JET tokamak with the ITER-Like Wall (ILW) and full tritium campaigns that preceded and followed after the DTE2, a sequence of fuel recovery methods was applied to promote tritium removal from wall c ...

Building on prior analysis of ASDEX Upgrade (AUG) experiments (Henderson et al 2023 Nucl. Fusion 63 086024), this study compares simple analytical formula predictions for divertor detachment onset and reattachment timescales in JET experiments. Detachment ...

ITER is of key importance in the European fusion roadmap as it aims to prove the scientific and technological feasibility of fusion as a future energy source. The EUROfusion consortium of labs within Europe is contributing to the preparation of ITER scient ...

The first results of three-dimensional, flux-driven, electrostatic, global, two-fluid turbulence simulations of a diverted tokamak configuration with applied resonant magnetic perturbations generated by a set of saddle coils are presented. The simulations ...

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The react-and-wind technique for manufacturing of large Nb3Sn fusion magnets (RW) is very attractive because of the superior performance of the Nb3Sn with lower thermal strain compared to the wind-and-react technique. The procedure for magnet winding is al ...

Numerical simulations explore a possible tightly baffled, long-legged divertor (TBLLD) concept in a future upgrade of the tokamak à configuration variable (TCV). The SOLPS-ITER code package is used to compare the exhaust performance of several TBLLD config ...

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This thesis presents advancements in the understanding of the plasma conditions leading to the excitation and saturation of the Edge Harmonic Oscillations (EHOs) observed during QH-mode operation in tokamak plasmas. Such operations represent a safer altern ...

The performance of magnetic confinement fusion devices, such as tokamaks, is strongly correlated to the phenomena that occur in the boundary region of the plasma core that faces the wall of the device. The dominant cross-field transport mechanisms from the ...

On ASDEX Upgrade a prioritized ‘advanced Tokamak’ program has been run during the last two experimental campaigns, focusing on the effect of non-standard current profiles on the behavior of high beta plasmas. Two lines of non-standard (i.e. non-sawtoothing ...

Plasma-molecular interactions generate molecular ions which react with the plasma and contribute to detachment through molecular activated recombination (MAR), reducing the ion target flux, and molecular activated dissociation (MAD), both of which create e ...

Benchmark of a self-consistent dynamic 1D divertor model DIV1D using the 2D SOLPS-ITER code

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Optical emission spectroscopy and microwave reflectometry for magnetised plasmas: Applications to ion sources and fusion machines

Spectroscopic characterisation of TCV divertor towards a detached regime

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

3D Characterisation of Turbulent Plasma Filaments Using Gas Puff Imaging in the Tokamak à Configuration Variable

Inter-discharge optimization for fast, reliable access to ASDEX Upgrade advanced tokamak scenario

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

Numerical study of divertor detachment in TCV H-mode scenarios

Tritium removal from JET-ILW after T and D-T experimental campaigns

Comparison of reduced model predictions for divertor detachment onset and reattachment timescales in ASDEX Upgrade and JET experiments

EUROfusion contributions to ITER nuclear operation

Plasma turbulence simulations in a diverted tokamak with applied resonant magnetic perturbations

Gyrokinetic turbulence modeling of a high performance scenario in JT-60SA

Bending Tolerance of React&Wind Nb3Sn Conductors for Fusion Magnets

Performance assessment of a tightly baffled, long-legged divertor configuration in TCV with SOLPS-ITER

Overview of fast particle experiments in the first MAST Upgrade experimental campaigns

Exploration of the parameter space for the excitation and saturation of Edge Harmonic Oscillations

Divertor turbulence characterisation using Gas Puff Imaging in the TCV tokamak

Flux pumping studies and Ti peaking by q-profile shaping using ECCD in ASDEX Upgrade

Investigating the impact of the molecular charge-exchange rate on detached SOLPS-ITER simulations