Concept

Écran à plasma

Publications associées (32)

Ultra‐High‐Efficiency On‐Chip CO 2 Conversion by Nanosecond Self‐Pulsing Micro‐Plasma Devices

Conversion of CO 2 into carbon‐neutral fuels and chemicals remains a central challenge in sustainable chemistry and energy sectors, as conventional catalytic processes are critically limited by the thermodynamic equilibrium and low overall energy efficiency. Here, a micro‐plasma chip for CO 2 ‐to‐CO conversion is introduced that achieves ultra‐high energy efficiency and breaks the thermodynamic equilibrium limitation under ambient conditions. These micro‐plasma devices (MPDs) with sub‐10‐µm discharge gaps s

Wiley2026

Tunable Lipid Coatings Enable Cytoplasmic siRNA Delivery by DNA Origami

DNA origami nanostructures (DONs) offer precise architectural control for small RNA delivery, but their performance is limited by their susceptibility to nuclease degradation, weak cellular uptake, and inefficient endosomal escape. Here, we introduce an electrostatic lipid-coating strategy that introduces membrane-like properties to DONs while maintaining their structural integrity. By coincubating folded DONs with liposomes composed of a defined mixture of zwitterionic and cationic lipids, we identify a fo

American Chemical Society2026

FGE: A Fast Free-Boundary Grad-Shafranov Evolutive Solver

Olivier Sauter

Accurate and rapid simulation of the free boundary tokamak plasma equilibrium evolution is essential for modern plasma control, stability analysis, and scenario development. This paper presents the Free-Boundary Grad-Shafranov Evolutive (FGE) code, a highly flexible and control-oriented solver designed to address the challenges posed by advanced plasma configurations across a range of devices. FGE evolved from the FBT [Hofmann, 1988] and LIUQE [Moret et al., 2015] codes and is part of the MEQ suite, sharing

IOP Publishing2026

Identifying non-performing or Dud Plasmas for Burning Plasma Control: Insights from JET and TFTR Deuterium-Tritium Campaigns

Among the burning plasma controllers for research fusion reactors, the dud detector will be of primary importance as it determines whether the plasma is performing well or if it is a dud. In the latter case, the discharge needs to be terminated to remain within tritium and neutron activation limits. To this scope, monitors which track the plasma performance will be integrated in the plasma control system. In this work, we present a novel dud detector that has been empirically identified based on Deuterium-T

IOP Publishing2026

Numerical model for pellet rocket acceleration in PELOTON

A direct numerical simulation model for the rocket acceleration of pellets in thermonuclear fusion devices has been developed for PELOTON, a 3D Lagrangian particle pellet code [R. Samulyak et al, Nuclear Fusion 61 (4), 046007 (2021)], and validated using shattered pellet injection (SPI) experiments in JET. The pellet rocket acceleration is driven by grad-B drift of the ablation cloud that creates asymmetry and non-uniform heating of the cloud. The model accounts for non-uniform charging of the ablation clou

IOP Publishing Ltd2026

Model-based Estimation of Tokamak Plasma Profiles and Physics Parameters: Integration with Improved Equilibrium Reconstruction and Experimental Data

Olivier Sauter

Plasma state reconstruction methods combining measurements and physics modeling improve the estimation of physics quantities in real-time and in post-discharge analysis. We present a workflow to reconstruct the dynamic evolution of a set of internal tokamak plasma profiles with consistent equilibria, as applied in this paper for experimental data from TCV L and H-mode discharges. Plasma profile estimates for electron temperature Te, electron density ne and parallel current density jpar are obtained by data

IOP Publishing Ltd2026

Study of the fast-ion confinement via velocity-space resolved measurements in several plasma scenarios in the TCV tokamak

The Fast Ion Loss Detector (FILD), installed on TCV in 2020 was redesigned and upgraded several times throughout this PhD. The collimator apertures were reduced to increase the energy resolution, a faster CMOS camera was intalled, a novel fast camera (up to 4 MHz) was installed to access microsecond velocity-space mapping, two more slits were added on the bottom partof the FILD head accessing to all magnetic field configurations, a bandpass optical filter was installed to reduce residual light contamination

EPFL2026

A procedure for rule extraction from a Self-Organising plasma disruption predictor for JET

Olivier Sauter, Stefano Coda, Basil Duval, Timothy Goodman, Jean-Marc Moret, Patrick Blanchard, Holger Reimerdes

In a previous paper, a Self-Organizing Map had proven to be able to identify the regions of the plasma operative space characterizing the pre-disruptive phase at JET without relying on any a priori information. One of the strengths of this disruption predictor lies in its inherent self-organization capability. The Self-Organizing Map discovers non-trivial relationships and captures the complicated interplay of device diagnostics on the internal plasma states directly from the experimental data. Moreover, th

2026

An adaptive quasi-neutrality solver for full-F flux-driven gyrokinetic simulations of tokamak plasmas in presence of poloidal asymmetries

Gyrokinetic codes are used to simulate transport in tokamak plasmas. In these codes, the distribution functions evolve self consistently with an electromagnetic field. To compute the temporal evolution of the electrostatic potential, a quasi-neutrality equation is solved. In some gyrokinetic codes, the quasi-neutrality solver assumes that the background densities and temperatures are constant in time and on flux surfaces. This assumption, which implicitly uses the so-called δF approach, can break up, in par

Centre pour la Communication Scientifique Directe (CCSD)2026

Results from the last DD and DT JET campaigns in the framework of the EUROfusion Tokamak Exploitation Work Package Activity

JET, the only tokamak capable of operating with deuterium-–tritium (D-T) fuel (since TFTR was shutdown in 1999), has provided essential experimental data to support ITER and DEMO design and operation. Within the EUROfusion Tokamak Exploitation Work Package, JET completed its final campaigns (2022--2023), culminating in the third D-T campaign (DTE3). These experiments addressed key challenges in plasma scenarios, exhaust control, and tritium management under reactor-relevant conditions. Significant progress

IOP Publishing2026

Growth, Characterization and Adhesion of Thick Deposited Tungsten Layers Under Transient Loading in Magnum-PSI

The recent decision by ITER to move from a Be to a W first wall has significant implications for material transport and deposition, and can be expected to lead to increased W layer growth rate in deposition regions, which may flake leading to plasma disruption. In this work a novel sputtering set-up was implemented in the Magnum-PSI linear plasma device to create W layers under ITER relevant conditions. A W plate was inserted into the plasma edge and biased to cause sputtering of W in an Ar plasma. This spu

IOP Publishing Ltd2026

Global gyro-kinetic Ion Temperature Gradient and Trapped Electron Mode turbulence modelling in X-point geometry in negative and positive triangularity

Stefano Coda

Comparative modelling of ITG/TEM turbulence in negative (NT) and positive (PT) triangularity plasma shapes was done using the nonlinear full-f global gyrokinetic particle code JOREK-GK in the realistic X-point tokamak geometry including the Scrape Off Layer (SOL) for TCV and DIII-D parameters. A comparison of JOREK-GK code with the gyrokinetic codes GS2 and GENE was done using NT/PT triangularity TCV L-modes parameters showing good agreement between codes in linear growth rates and clear beneficial effect o

IOP Publishing2026

Overview of the MAST Upgrade physics programme: testing novel concepts at low aspect ratio to inform future devices

Olivier Sauter, Holger Reimerdes

The research programme performed on the Mega Amp Spherical Tokamak (MAST) Upgrade experiment has made significant advances in developing the physics understanding of low aspect ratio tokamaks in support of the operation of ITER and design of fusion powerplants. High performance plasma scenarios have been developed to facilitate a broad programme of experiments, in which confinement is constrained by the presence of m/n = 2/1 modes that cause substantial losses of fast ions. The onset of these modes coincide

IOP Publishing Ltd2026

Non-inductive high-performance discharges on TCV on the path to steady state

Olivier Sauter, Stefano Coda

An extended experimental effort is underway on the TCV tokamak to develop scenarios compatible with long-pulse operation, featuring mostly non-inductively driven current – preferably with a large fraction of bootstrap current. A closely related goal is to achieve good plasma performance, typically measured through the normalized beta beta_N. This work is part of a broader endeavor involving several European tokamaks, under the auspices of the Tokamak Exploitation Work Package (WPTE) of EUROfusion, and aimed

IOP Publishing2026

Fast ion transport in complex magnetic field configurations in TORPEX

Suprathermal ions, i.e. ions with energies exceeding those of the bulk plasma, arise in diverse natural and laboratory plasmas ranging from the solar wind to magnetic confinement fusion (MCF) devices. In tokamaks, they are generated by external heating systems and fusion reactions, and a thorough characterization of their dynamics is crucial for safe operation. In tokamaks, the core plasma is separated from the walls by the last closed flux surface (LCFS), which exhibits a null point (X-point) in the poloid

EPFL2026

Advancing Hydrogen Rich Syngas Production: Biomass and Waste Plasma Pyrolysis and Gasification Technologies

Hubert Girault

Hydrogen produced from biomass and waste via plasma technologies offers a sustainable pathway for clean energy generation while addressing waste management challenges. This review examines recent advancements in plasma pyrolysis and gasification for hydrogen production, comparing thermal (microwave, gliding arc, plasma torches) and non-thermal (dielectric barrier discharge, glow discharge) plasmas. Beyond, summarizing recent developments, this review provides an integrated comparison of thermal and non-ther

Springer Science and Business Media LLC2026

Optimised 'hybrid' Scenario H-mode Plasmas for W Radiation Control in Jet with the Be/w Wall

Screening of high-Z (W) impurities from the confined plasma by the temperature gradient at the plasma periphery of fusion-grade H-mode plasmas was demonstrated for the first time in JET with the Be/W wall (Field et al 2023 Nucl. Fusion 63 016028). Additional experiments have been performed in JET during 2023, including in deuterium-tritium (DT) during the DTE3 campaign, to further optimise the impurity screening in such plasmas, as well as our bolometric measurements of the W impurity fluxes between and dur

IOP Publishing Ltd2026

Status of the 3 MW ECRH System at 105 GHz for WEST

W environment in steady-state tokamak (WEST) experiments aim to achieve long plasma pulses (1000 s) and to expose ITER-like tungsten divertor to power fluxes up to 10 MW/m2. To increase the margin to reach H-Mode regimes and control W-impurities in the plasma, the WEST ECRH system is upgraded to a power capability of 3 MW/1000 s at the frequency of 105 GHz. The Tore Supra ECRH antenna has first been improved and is now installed in the equatorial plane of WEST to start ECRH operation on plasma. On the power

Institute of Electrical and Electronics Engineers (IEEE)2026

A multi-model system-identification comparison with the global particle dynamics in TCV

Holger Reimerdes

In this work, we compare physics-based dynamic exhaust models with frequency response measurements (FRMs) of the global particle dynamics in the Tokamak à Configuration Variable (TCV). The aim is to understand and model the experimental in-vessel dynamic response of plasma and neutrals to deuterium gas puff modulations with three models of varying fidelity: a 0D three chamber model (TCM); DIV1D, which models the edge plasma in 1D, and SOLEDGE3X for 2D-axisymmetric modeling. We find that the dynamic behavior

IOP Publishing Ltd2026

Tungsten erosion and scrape-off layer transport modelling in L-mode helium plasma discharges in ASDEX Upgrade

Due to its unavoidable presence in thermonuclear DT plasmas and to its peculiar effects on materials, investigating the role of helium (He) in plasma-wall interaction (PWI) in current tokamaks is fundamental. In this work, PWI in L-mode He plasma discharges in ASDEX Upgrade (AUG) is modelled by exploiting simplified analytical approaches and two state-of-the-art codes. SOLPS-ITER is employed both to provide a suitable background plasma for erosion simulations and to interpret diagnostics measurements in ter

IOP Publishing2026

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