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

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Plasma edge simulations with the SOLPS-ITER code are performed to study the influence of divertor baffles on nitrogen-seeded detachment in Tokamak & agrave; Configuration Variable (TCV) single-null, L-mode discharges. Scans of nitrogen seeding rate are con ...

Plasma shape control is a fundamental tool for effective tokamak operation, allowing improved plasma performance and the pursuit of challenging scientific objectives. In this framework, the Tokamak á Configuration Variable (TCV) of the École Polytechnique ...

Helicon discharges are often considered somewhat mysterious, exhibiting experimental behaviors that are challenging to explain, such as abrupt plasma density jumps, hysteresis, and ‘blue core’ formation, among others. A significant part of the difficulty i ...

We analyze a measure for the degree of chaos in the magnetic fields of magnetic confinement fusion reactors by calculating the lobe fluxes of turnstiles - a method developed for characterizing transport into and out of resonance zones in Hamiltonian dynami ...

The plasma density is a crucial parameter of tokamak discharge as it impacts the fusion power, stability limits, influences detachment onset and impurities transport. The electron density profile shaping affects the deposition location of the external heat ...

The quasi-continuous exhaust (QCE) regime is a type-I ELM-free high confinement regime obtained at high plasma shaping and high separatrix density. A comparison with various ELM-free regimes in the literature is presented together with potential physics mo ...

In a previous paper, a new gyrokinetic quasilinear model was proposed to study turbulent momentum transport in tokamaks with up-down asymmetric plasma shaping and toroidal flow shear (Sun et al 2024 Nuclear Fusion 64 036026). In this work, we start by appl ...

In tokamaks, rotating magneto-hydro-dynamic modes frequently decelerate as their amplitude increases. Once a critical threshold in amplitude is reached, these modes stop rotating into a specific toroidal and poloidal position and are commonly named Locked ...

In order to cope with the decarbonization challenge faced by many countries, fusion is one of the few alternatives to fossil fuels for the production of electricity. Two devices invented in the middle of the previous century have emerged as the most promis ...

Nuclear fusion presents a promising clean energy source to mitigate future energy crises, with magnetic confinement fusion well-positioned to provide a baseload scenario to power future reactors. The unmitigated power exhaust of such reactors threatens its ...

The parameter R D = P rad / P cond , which measures the ratio of radiated power to conductive heat flux at downstream Scrape-Off-Layer (SOL), is proposed as a robust and practically useful figure of merit for divertor detachment control. The simulations pe ...

The implementation of three-dimensional magnetic fields, such as the ones of stellarators, in the GBS code (Ricci et al 2012 Plasma Phys. Control. Fusion54 124047; Giacomin et al 2022 J. Comput. Phys.464 111294) is presented, and simulation results are dis ...

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 ...

This work explains the anomalously high runaway electron (RE) pitch angles inferred in the flat-top of dedicated Tokamak a Configuration Variable (TCV) experiments. Kinetic modelling shows that the resonant interaction between the gyromotion of the electro ...

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 ...

This paper discusses the development of a benign termination scenario for runaway electron (RE) beams on ASDEX Upgrade and TCV. A systematic study revealed that a low electron density (n e) companion plasma was required to achieve a large MHD instability, ...

Carbon impurity transport is studied in the TCV tokamak using a charge exchange recombination diagnostic. TCVs flexible shaping capabilities were exploited to extend previous impurity transport studies to negative triangularity (delta < 0). A practical way ...

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 ...

DEMO will have a limited diagnostic set for optimization of reactor performance, and limited diagnostic coverage due to challenging reactor conditions. This poses challenges for control, especially for detachment control which is planned to be performed wi ...

Using newly developed spectroscopic models to measure the divertor concentration of Ne and Ar, it is shown that the experimental detachment threshold on ASDEX Upgrade with Ar-only and mixtures of Ar+N or Ne+N scales as expected in comparison with an analyt ...

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

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Investigating the influence of divertor baffles on nitrogen-seeded detachment in TCV with SOLPS-ITER simulations and TCV experiments

Design and implementation of a model-based hierarchical architecture for plasma shape control in the TCV tokamak

Helicon normal modes in radially non-uniform plasma column

Turnstile flux as a measure for chaotic transport in magnetic confinement fusion devices

Real-time density profile simulations on ASDEX Upgrade and the impact of the edge boundary condition

The quasi-continuous exhaust regime in ASDEX Upgrade and JET

A Quasilinear Model for Momentum Transport Including Rotation and Electron-scale Turbulence

Machine learning methods for locked-mode predictions in MAST-U plasmas

Global fluid simulations of plasma turbulence in stellarators

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

Numerical study of a general criterion for divertor detachment control

Global fluid simulation of plasma turbulence in stellarators with the GBS code

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

Resonant interaction between runaway electrons and the toroidal magnetic field ripple in TCV

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

Benign termination of runaway electron beams on ASDEX Upgrade and TCV

Study of impurity C transport and plasma rotation in negative triangularity on the TCV tokamak

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

Demonstration of a sparse sensor placement technique to the limited diagnostic set in a fusion power plant

Divertor detachment and reattachment with mixed impurity seeding on ASDEX Upgrade