Analysis and expansion of the quasi-continuous exhaust (QCE) regime in ASDEX Upgrade

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Combining dynamic models and measurements into a consistent plasma state estimate is an important challenge for ITER and DEMO, due to the inherent limitations regarding diagnostic coverage in a nuclear fusion reactor environment. In this work, a model-base ...

Understanding cross field heat and particle transport is crucial in tokamaks, especially in the X-point and divertor regions. However, the complex magnetic field geometry and the associated turbulent and drift phenomena lead to large heat fluxes, rendering ...

The pre-thermal quench (pre-TQ) dynamics of a pure deuterium ( D 2 ) shattered pellet injection (SPI) into a 3 MA / 7 MJ JET H-mode plasma is studied via 3D non-linear MHD modelling with the JOREK code. The interpretative modelling captures the overall evo ...

Massive material injections in the JET tokamak have been observed to substantially affect resistive bolometer measurements, resulting in a spurious radiated power signal proportional to the quantity injected and reaching up to 8 MW. These bolometers are ca ...

Runaway electrons (REs) created during tokamak disruptions pose a threat to the reliable operation of future larger machines. Experiments using shattered pellet injection (SPI) have been carried out at the JET tokamak to investigate ways to prevent their g ...

A series of experiments have been executed at JET to assess the efficacy of the newly installed shattered pellet injection (SPI) system in mitigating the effects of disruptions. Issues, important for the ITER disruption mitigation system, such as thermal l ...

The stepped-pressure equilibrium code (SPEC) (Hudson et al., Phys. Plasmas, vol. 19, issue 11, 2012, 112502) is extended to allow the computation of multi-region, relaxed magnetohydrodynamics (MRxMHD) equilibria at prescribed toroidal current profile. Toro ...

The physics of the tokamak pedestal is still not fully understood, for example there is no fully predictive model for the pedestal height and width. However, the pedestal is key in determining the fusion power for a given scenario. If we can improve our un ...

JOREK is a massively parallel fully implicit non-linear extended magneto-hydrodynamic (MHD) code for realistic tokamak X-point plasmas. It has become a widely used versatile simulation code for studying large-scale plasma instabilities and their control an ...

In the last few years, the current density of Bi-2212 wires has been greatly improved by filament densify technologies. One further step toward applications in fusion magnets is to design a high current cable, which must overcome the drawbacks of Bi-2212 w ...

In some JET discharges, type-I edge localised modes (ELMs) are preceded by a class of low-frequency oscillations (Perez et al 2004 Nucl. Fusion 44 609). While in many cases the ELM is triggered during the growth phase of this oscillation, it is also observ ...

Macroscopic instabilities and their unfavourable effects on plasma confinement pose a central challenge for the development of reactor relevant tokamak scenarios. Some promising operation scenarios feature extended regions of low magnetic shear. These are ...

A series of experiments has been conducted at AUG and TCV to disentangle the role of fueling, plasma triangularity and closeness to a double null (DN) configuration for the onset of the small ELM regime. At AUG, the role of the SOL density has been revisit ...

Integrating the plasma core performance with an edge and scrape-off layer (SOL) that leads to tolerable heat and particle loads on the wall is a major challenge. The new European medium size tokamak task force (EU-MST) coordinates research on ASDEX Upgrade ...

Through a diverse research programme, the Tokamak a Configuration Variable (TCV) addresses physics issues and develops tools for ITER and for the longer term goals of nuclear fusion, relying especially on its extreme plasma shaping and electron cyclotron r ...

Developing modern software typically involves composing functionality from existing libraries. This task is difficult because libraries may expose many methods to the developer. To help developers in such scenarios, we present a technique that synthesizes ...

The Tokamak concept, based on magnetic confinement of a hydrogen plasma, is one of today's most promising paths to energy production by nuclear fusion. The experimental scenarios leading to the largest fusion rate are based on a high confinement plasma reg ...

The spectral broadening of characteristic gamma-ray emission peaks from the reaction C-12(He-3, p gamma)N-14 was measured in D(He-3) plasmas of the JET tokamak with ion cyclotron resonance heating tuned to the fundamental harmonic of He-3. Intensities and ...

Numerical simulation of the tokamak scrape-off layer (SOL) is an essential tool for the prediction of the conditions to be expected in future fusion reactors such as the ITER project, now under construction in Southern France. One particularly important is ...

The theoretical study of plasma turbulence is of central importance to fusion research. Experimental evidence indicates that the confinement time results mainly from the turbulent transport of energy, the magnitude of which depends on the turbulent state r ...

Analysis and expansion of the quasi-continuous exhaust (QCE) regime in ASDEX Upgrade

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Model-based estimation of tokamak plasma profiles and physics parameters: algorithm overview and application to ITER

Impact of the magnetic shear on plasma equilibrium and turbulent transport in the vicinity of an X-point in TORPEX

Interpretative 3D MHD modelling of deuterium SPI into a JET H-mode plasma

Spurious radiated power signal following massive material injections in JET and the effect of neutral gas pressure on resistive bolometers

Physics of runaway electrons with shattered pellet injection at JET

Shattered pellet injection experiments at JET in support of the ITER disruption mitigation system design

Computation of multi-region, relaxed magnetohydrodynamic equilibria with prescribed toroidal current profile

Towards understanding reactor relevant tokamak pedestals

The JOREK non-linear extended MHD code and applications to large-scale instabilities and their control in magnetically confined fusion plasmas

Design Study of a 50-kA React-and-Wind Bi-2212 Cable for Fusion Magnet

Long-lived coupled peeling ballooning modes preceding ELMs on JET

Non-linear modelling of saturated internal and external MHD instabilities in tokamaks

PLASMA SHAPE AND FUELING DEPENDENCE ON THE SMALL ELMS REGIME IN TCV AND AUG

Overview of progress in European medium sized tokamaks towards an integrated plasma-edge/wall solution

Overview of recent and current research on the TCV tokamak

Complete Completion using Types and Weights

Edge Localized Mode Control in TCV

Spectral Broadening of Characteristic gamma-Ray Emission Peaks from C-12(He-3, p gamma)N-14 Reactions in Fusion Plasmas

SOLPS modelling of ELMing H-mode

The role of plasma elongation on turbulent transport in magnetically confined plasmas