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Concept

Plasma confinement

Publications associées (28)

Towards practical reinforcement learning for tokamak magnetic control

Federico Alberto Alfredo Felici, Jonas Buchli, Cristian Galperti

Reinforcement learning (RL) has shown promising results for real-time control systems, including the domain of plasma magnetic control. However, there are still significant drawbacks compared to traditional feedback control approaches for magnetic confinem ...

Elsevier Science Sa2024

Re-design of EU DEMO with a low aspect ratio

Xabier Sarasola Martin

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, ...

Elsevier2024

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

Sophie Danielle Angelica Gorno

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 ...

EPFL2024

Integrated modelling of neon impact on JET H-mode core plasmas

Yann Camenen, Michele Marin

Nuclear fusion reactor plasmas will need to exhaust a significant proportion of energy flux through radiative processes, to enable acceptable divertor loads. This can be obtained by line radiation from impurities, injected from the plasma edge. There are h ...

IOP Publishing Ltd2023

A machine-learning-based tool for last closed-flux surface reconstruction on tokamaks

Olivier Sauter, Alessandro Pau

Tokamaks allow to confine fusion plasma with magnetic fields. The prediction/reconstruction of the last closed-flux surface (LCFS) is one of the primary challenges in the control of the magnetic configuration. The evolution in time of the LCFS is determine ...

IOP Publishing Ltd2023

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

Nicola Offeddu

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 ...

EPFL2023

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

Guillaume Michel Le Bars

Gyrotrons are a class of high-power vacuum-electronics microwave sources, which are envisioned to play an important role in the domain of magnetically confined fusion plasmas. Indeed, only gyrotrons are capable of producing continuous electromagnetic waves ...

EPFL2023

Magnetic control of tokamak plasmas through deep reinforcement learning

Olivier Sauter, Basil Duval, Stefano Coda, Ambrogio Fasoli, Jean-Marc Moret, Federico Alberto Alfredo Felici, Cristian Sommariva, Antoine Pierre Emmanuel Alexis Merle, Cristian Galperti, Jonas Buchli, Francesco Carpanese, Federico Pesamosca

Nuclear fusion using magnetic confinement, in particular in the tokamak configuration, is a promising path towards sustainable energy. A core challenge is to shape and maintain a high-temperature plasma within the tokamak vessel. This requires high-dimensi ...

2022

Experimental confirmation of efficient island divertor operation and successful neoclassical transport optimization in Wendelstein 7-X

Jieping Zhu, Nicola Vianello, Jonathan Marc Philippe Faustin, Eduardo Sanchez, Jonathan Graves, Alberto Bottino, Emiliano Fable, Joaquim Loizu Cisquella, Frank Rüdiger Wagner, Thomas Binderup Jensen, Attila Bencze, Gregory Vogel, Antoine Baillod, Mike Machielsen

We present recent highlights from the most recent operation phases of Wendelstein 7-X, the most advanced stellarator in the world. Stable detachment with good particle exhaust, low impurity content, and energy confinement times exceeding 100 ms, have been ...

IOP Publishing Ltd2022

Superconductors for fusion: a roadmap

Pierluigi Bruzzone, Rainer Wesche, Kamil Sedlák, Nikolay Bykovskiy

With the first tokamak designed for full nuclear operation now well into final assembly (ITER), and a major new research tokamak starting commissioning (JT60SA), nuclear fusion is becoming a mainstream potential energy source for the future. A critical par ...

IOP Publishing Ltd2021

Physics and applications of three-ion ICRF scenarios for fusion research

Henri Weisen, Javier García Hernández, Mikhail Maslov, Samuele Mazzi

This paper summarizes the physical principles behind the novel three-ion scenarios using radio frequency waves in the ion cyclotron range of frequencies (ICRF). We discuss how to transform mode conversion electron heating into a new flexible ICRF technique ...

2021

Power exhaust by core radiation at COMPASS tokamak

Olivier Claude Martin Février, Davide Mancini

Substantial power dissipation in the edge plasma is required for the safe operation of ITER and next-step fusion reactors, otherwise unmitigated heat fluxes at the divertor plasma-facing components (PFCs) would easily exceed their material limits. Traditio ...

IOP Publishing Ltd2021

A phase-contrast-imaging core fluctuation diagnostic and first-principles turbulence modeling for JT-60SA

Stefano Coda, Stephan Brunner, Matthieu Toussaint, Aylwin Iantchenko

A core fluctuation diagnostic based on the phase-contrast imaging (PCI) technique has been designed for the JT-60SA tokamak, with the assistance of a synthetic diagnostic coupled to a gyrokinetic code. Using a tangentially viewing geometry, this system wou ...

IOP Publishing Ltd2021

Approaching detachment in I-mode-response of core confinement and the edge pedestal in the ASDEX Upgrade tokamak

Antoine Pierre Emmanuel Alexis Merle

Experiments on nitrogen assisted divertor detachment in the improved energy confinement mode (I-mode) are reported from the ASDEX Upgrade tokamak. When nitrogen is introduced into the divertor and radiation losses cool the divertor plasma down, a loss of c ...

IOP Publishing Ltd2021

Neutronics Analyses of EU DEMO 2020 EC Port Configuration

Minh Quang Tran, René Chavan

The DEMOnstration fusion power plant (DEMO) is being developed within EUROfusion and one of the challenges is the integration of all the systems into a fusion reactor by designs that meet strict design criteria required for safe and reliable long-term reac ...

NUCLEAR SOCIETY SLOVENIA2021

A Fast Ion Loss Detector for the TCV Tokamak

Lorenzo Stipani

A Fast Ion Loss Detector (FILD) was designed, assembled, installed and commissioned for TCV. This is a radially positionable, scintillator based detector that provides information on the 2D fast-ion velocity space lost at the probe's location. The collecte ...

EPFL2021

Assessment of alternative divertor configurations as an exhaust solution for DEMO

Holger Reimerdes, Roberto Maurizio

Plasma exhaust has been identified as a major challenge towards the realisation of magnetic confinement fusion. To mitigate the risk that the single null divertor (SND) with a high radiation fraction in the scrape-of-layer (SOL) adopted for ITER will not e ...

IOP Publishing Ltd2020

Analysis of the inter-species power balance in JET plasmas

Henri Weisen, Mikhail Maslov

Most auxiliary heating methods provide heating to more than one particle species (electrons, ions, impurities) in a fusion plasma. This can lead to substantial temperature differences between species, depending on conditions such as heating power to the di ...

IOP Publishing Ltd2020

EDGE2D-EIRENE simulations of the influence of isotope effects and anomalous transport coefficients on near scrape-off layer radial electric field

Olivier Sauter, Basil Duval, Henri Weisen, Martinus Adela Maria Gijs, Jonathan Graves, Ambrogio Fasoli, Stefano Coda, Patrick Blanchard, Richard Pitts, Yves Martin, Yann Camenen, Javier García Hernández, Duccio Testa, Marco Wischmeier, Miguel Fernández Ruiz, Nicola Vianello, Sun Hee Kim, Federico Nespoli, Alessandro Pau, David Pfefferlé, Davide Galassi, Jonathan Marc Philippe Faustin, Dalziel Joseph Wilson, Cristian Sommariva, Hamish William Patten, Samuel Lanthaler, Jan Horacek, José Pedro Rebelo Ferreira Marques, Mikhail Maslov, Liang Yao, Daniel Scott Alessi, Jonnathan Cesar Hidalgo Acosta, Antonio José Pereira de Figueiredo, Alberto Hernando de Castro, Julio Rodriguez, Li Shuai, Rebecca Hill

EDGE2D-EIRENE (the 'code') simulations show that radial electric field, Er, in the near scrape-off layer (SOL) of tokamaks can have large variations leading to a strong local E x B shear greatly exceeding that in the core region. This was pointed out in si ...

2019

Disruption Prediction Approaches Using Machine Learning Tools in Tokamaks

Alessandro Pau

Nuclear fusion is one of the best options to achieve a virtually limitless energy source in the future. However, sustaining burning plasma reactions is very challenging because disruptive events cause the loss of plasma confinement and damages to the tokam ...

IEEE2019

Publications associées (28)

Experimental confirmation of efficient island divertor operation and successful neoclassical transport optimization in Wendelstein 7-X

IOP Publishing Ltd2022

EDGE2D-EIRENE simulations of the influence of isotope effects and anomalous transport coefficients on near scrape-off layer radial electric field

2019

Disruption Prediction Approaches Using Machine Learning Tools in Tokamaks

Alessandro Pau

IEEE2019