Publications related to Measurement of tokamak error fields using plasma response and its applicability to ITER

Preliminary Design of a High Current R&W TF Coil Conductor for the EU DEMO

Pierluigi Bruzzone, Kamil Sedlák, Federica Demattè

Paschen failures in ITER, W7-X and JT60 superconducting coils at the acceptance tests have shown that it is highly desirable to lower the coil discharge voltage (U-d) of the DEMO Toroidal Field (TF) coils. Another benefit of lowering the U-d might be the r ...

IEEE-INST ELECTRICAL ELECTRONICS ENGINEERS INC2022

On the Ohmic-dominant heating mode of capacitively coupled plasma inverted by boundary electron emission

Haomin Sun, Guang-Yu Sun

Electron emission from the boundary is ubiquitous in a capacitively coupled plasma (CCP) and precipitates nonnegligible influence on the discharge properties. Here, we present Particle-in-Cell/Monte Carlo Collision simulation of an Ohmic-dominant heating m ...

2022

New insights on divertor parallel flows,E x B drifts, and fluctuations from in situ, two-dimensional probe measurement in the Tokamak a Configuration Variable

Basil Duval, Holger Reimerdes, Christian Gabriel Theiler, Artur Perek, Sophie Danielle Angelica Gorno, Cedric Kar-Wai Tsui, Hugo De Oliveira

In situ, two-dimensional (2D) Langmuir probe measurements across a large part of the TCV outer divertor are reported in L-mode discharges with and without divertor baffles. This provides detailed insights into time averaged profiles, particle fluxes, and f ...

IOP Publishing Ltd2022

Model-based optimization of magnetic control in the TCV tokamak: design and experiments

Federico Pesamosca

Thermonuclear controlled fusion is a promising answer to the current energy and climate issues, providing a safe carbon-free source of energy which is virtually inexhaustible. In magnetic confinement thermonuclear fusion based on tokamak reactors, hydrogen ...

EPFL2021

First global simulations of plasma turbulence in a stellarator with an island divertor

Paolo Ricci, Joaquim Loizu Cisquella, António João Caeiro Heitor Coelho

We present the results of 3D, flux-driven, global, two-fluid electrostatic turbulence simulations in a 5-field period stellarator with an island divertor. The numerical simulations are carried out with the GBS code, which solves the two-fluid drift-reduced ...

2021

In next step tokamaks such as ITER and future fusion power plants, wall materials will be subjected to considerably higher heat and particle fluxes than in present-day machines. Maintaining plasma facing components in good condition and simultaneously assu ...

EPFL2021

Integrated Real-Time Supervisory Management for Off-Normal-Event Handling and Feedback Control of Tokamak Plasmas

Olivier Sauter, Alessandro Pau, Federico Alberto Alfredo Felici, Cristian Galperti, Bernhard Sieglin

For long-pulse tokamaks, one of the main challenges in the control strategy is to simultaneously reach multiple control objectives and to robustly handle in real-time (RT) unexpected events [off-normal-events (ONEs)] with a limited set of actuators. We hav ...

IEEE-INST ELECTRICAL ELECTRONICS ENGINEERS INC2021

Real-time feedback control system for ADITYA-U horizontal plasma position stabilisation

Harshita Raj, Rohit Kumar, Shivam Gupta

The ADITYA-U tokamak (R-0 = 0.75 m, a = 0.25 m) is designed to shape plasma column in both single and double null diverter configurations. It is quite well known that sustaining a shaped plasma in tokamak requires very good plasma column position control, ...

2021

Towards integrated control of tokamak plasmas: physics-based control of neoclassical tearing modes in the TCV tokamak

Mengdi Kong

Neoclassical tearing modes (NTMs), magnetic islands located at rational

q

surfaces, are an important class of resistive magnetohydrodynamics (MHD) instabilities in tokamak plasmas, with

q

the safety factor. NTMs are one of the main constraints of the a ...

EPFL2020

DEMO physics challenges beyond ITER

Olivier Sauter, Emiliano Fable, Hartmut Zohm

For electricity producing tokamak fusion reactors like EU-DEMO, it is prudent to choose a plasma scenario close to the ITER baseline, where the largest amount of experimental evidence is available. Nevertheless, there are some aspects in which ITER and EU- ...

2020

Measurement of tokamak error fields using plasma response and its applicability to ITER

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Preliminary Design of a High Current R&W TF Coil Conductor for the EU DEMO

On the Ohmic-dominant heating mode of capacitively coupled plasma inverted by boundary electron emission

New insights on divertor parallel flows,E x B drifts, and fluctuations from in situ, two-dimensional probe measurement in the Tokamak a Configuration Variable

Model-based optimization of magnetic control in the TCV tokamak: design and experiments

First global simulations of plasma turbulence in a stellarator with an island divertor

Integrated Real-Time Supervisory Management for Off-Normal-Event Handling and Feedback Control of Tokamak Plasmas

Real-time feedback control system for ADITYA-U horizontal plasma position stabilisation

Towards integrated control of tokamak plasmas: physics-based control of neoclassical tearing modes in the TCV tokamak

DEMO physics challenges beyond ITER

On the Ohmic-dominant heating mode of capacitively coupled plasma inverted by boundary electron emission

Real-time feedback control system for ADITYA-U horizontal plasma position stabilisation

Preliminary Design of a High Current R&W TF Coil Conductor for the EU DEMO

Model-based optimization of magnetic control in the TCV tokamak: design and experiments

First global simulations of plasma turbulence in a stellarator with an island divertor

Towards integrated control of tokamak plasmas: physics-based control of neoclassical tearing modes in the TCV tokamak

New insights on divertor parallel flows,E x B drifts, and fluctuations from in situ, two-dimensional probe measurement in the Tokamak a Configuration Variable

Integrated Real-Time Supervisory Management for Off-Normal-Event Handling and Feedback Control of Tokamak Plasmas

DEMO physics challenges beyond ITER