Benoît Labit

benoit.labit@epfl.ch +41 21 693 45 62

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Nationality: French, Swiss

EPFL SB SPC-TCV
PPB 118 (Bâtiment PPB)
Station 13
1015 Lausanne

+41 21 693 45 62
Office: PPB 118
EPFL › SB › SPC › SPC-TCV

Website: https://spc.epfl.ch/

+41 21 693 45 62
EPFL › VPA › VPA-AVP-DLE › AVP-DLE-EDOC › EDPY-ENS

Expertise

H-mode physics
Plasma turbulence
Experimental physics
Numerical simulations

Current work

Deputy Task Force Leader for the EUROfusion Workpackage "Tokamak Exploitation"

Biography Publications Teaching & PhD

PhD Thesis

Tokamak electron heat transport by direct numerical simulation of small scale turbulence
In a fusion machine, understanding plasma turbulence, which causes a degradation of the measured energy confinement time, would constitute a major progress in this field. In tokamaks, the measured ion and electron thermal conductivities are of comparable magnitude. The possible sources of turbulence are the temperature and density gradients occurring in a fusion plasma. Whereas the heat losses in the ion channel are reasonably well understood, the origin of the electron losses is more uncertain. In addition to the the radial velocity associated to the fluctuations of the electric field, electrons are more affected than ions by the magnetic field fluctuations. In experiments, the confinement time can be conveniently expressed in terms of dimensionless parameters. Although still somewhat too imprecise, these scaling laws exhibit strong dependencies on the normalized pressure, β or the normalized Larmor radius, Ï*.
The present thesis assesses whether a tridimensional, electromagnetic, nonlinear fluid model of plasma turbulence driven by a specific instability can reproduce the dependence of the experimental electron heat losses on the dimensionless parameters β and Ï*. The investigated interchange instability is the Electron Temperature Gradient driven one (ETG). The model is built by using the set of Braginskii equations. The developed simulation code is global in the sense that a fixed heat flux is imposed at the inner boundary, leaving the gradients free to evolve.
From the nonlinear simulations, we have put in light three characteristics for the ETG turbulence: the turbulent transport is essentially electrostatic; the potential and pressure fluctuations form radially elongated cells called streamers; the transport level is very low compared to the experimental values.
The thermal transport dependence study has shown a very small role of the normalized pressure, which is in contradiction with the Ohkawa

Education

Docteur es Sciences

| mention Rayonnement et Plasmas

2002 – 2002 Universitï¿½ de Provence Aix-Marseille I
Directed by Dr. M. Ottaviani et Dr. D. F. Escande

Professionals experiences

Collaborateur scientifique

2009–2009

EPFL

Post-doc

2003–2008

EPFL

Doctorant

1999–2002

CEA Cadarache (F)

201311

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

F. Bagnato; B. P. Duval; O. Sauter; S. Coda; A. Karpushov et al.

Plasma Physics And Controlled Fusion

2024-07-01

DOI : 10.1088/1361-6587/ad5229

Benoît Labit

Expertise

Current work

PhD Thesis

Education

Docteur es Sciences

Professionals experiences

201311

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

* The effect of plasma shaping on high density H-mode SOL profiles and fluctuations in TCV

* Progress in the development of the ITER baseline scenario in TCV

* Effect of the isotope mass on pedestal structure, transport and stability in D, D/T and T plasmas at similar β N and gas rate in JET-ILW type I ELMy H-modes

* ICRH assisted breakdown study on JET

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

* Determination of MHD mode structures using soft x-ray diagnostics in TCV

* Overview of the TCV tokamak experimental programme

* Improved heat and particle flux mitigation in high core confinement, baffled, alternative divertor configurations in the TCV tokamak

* Prospects of core–edge integrated no-ELM and small-ELM scenarios for future fusion devices

* Quasicontinuous Exhaust Scenario for a Fusion Reactor: The Renaissance of Small Edge Localized Modes

* Full conversion from ohmic to runaway electron driven current via massive gas injection in the TCV tokamak

* Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario development

* Enhanced confinement in diverted negative-triangularity L-mode plasmas in TCV

* Detachment in conventional and advanced double-null plasmas in TCV

* Divertor closure effects on the TCV boundary plasma

* High resolution density pedestal measurements during edge localized modes by short-pulse reflectometry in the TCV tokamak

* Impact of the new TCV baffled divertor upgrade on pedestal structure and performance

* H-mode scrape-off layer power width in the TCV tokamak

* Pedestal structure, stability and scalings in JET-ILW: the EUROfusion JET-ILW pedestal database

* Numerical investigation of optimal divertor gas baffle closure on TCV

* Scrape-off layer transport and filament characteristics in high-density tokamak regimes

* Nitrogen-seeded divertor detachment in TCV L-mode plasmas

* Scrape Off Layer (SOL) transport and filamentary characteristics in high density tokamak regimes

* Status, scientific results and technical improvements of the NBH on TCV tokamak

* Role of the pedestal position on the pedestal performance in AUG, JET-ILW and TCV and implications for ITER

* Validation of the ICRF antenna coupling code RAPLICASOL against TOPICA and experiments

* ELM-induced cold pulse propagation in ASDEX Upgrade

* Overview of physics studies on ASDEX Upgrade

* Experimental implementation of a real-time power flux estimator for the ITER first wall on the TCV tokamak

* Langmuir probe electronics upgrade on the tokamak a configuration variable

* Real time magnetic control of the snowflake plasma configuration in the TCV tokamak

* An improved understanding of the roles of atomic processes and power balance in divertor target ion current loss during detachment

* Physics research on the TCV tokamak facility: from conventional to alternative scenarios and beyond

* A locked mode indicator for disruption prediction on JET and ASDEX upgrade

* A Variable Structure Control Scheme Proposal for the Tokamak a Configuration Variable

* Progress toward divertor detachment on TCV within H-mode operating parameters

* Dependence on plasma shape and plasma fueling for small edge-localized mode regimes in TCV and ASDEX Upgrade

* Application of a two-fluid two-point model to SolEdge2D-EIRENE simulations of TCV H-mode plasma

* Millimeter-wave beam scattering by edge-plasma density fluctuations in TCV

* Pedestal structure and energy confinement studies on TCV

* Conduction-based model of the Scrape-Off Layer power sharing between inner and outer divertor in diverted low-density tokamak plasmas

* The effect of the secondary x-point on the scrape-off layer transport in the TCV snowflake minus divertor

* Disruption avoidance through the prevention of NTM destabilization in TCV

* Parameter dependences of small edge localized modes (ELMs)

* Fluctuation characteristics of the TCV snowflake divertor measured with high speed visible imaging

* Filamentary velocity scaling validation in the TCV tokamak

* Impurity seeding for suppression of the near scrape-off layer heat flux feature in tokamak limited plasmas

* Analysis of wall-embedded Langmuir probe signals in different conditions on the Tokamak à Configuration Variable

* Dependence of the L-Mode scrape-off layer power fall-off length on the upper triangularity in TCV

* Experimental observations of modes with geodesic acoustic character from the core to the edge in the TCV tokamak

* Divertor power load studies for attached L-mode single-null plasmas in TCV

* Detachment evolution on the TCV tokamak

* TCV experiments towards the development of a plasma exhaust solution

* TCV divertor upgrade for alternative magnetic configurations

* Effect of plasma geometry on divertor heat flux spreading: MONALISA simulations and experimental results from TCV

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

* Modification of SOL profiles and fluctuations with line-average density and divertor flux expansion in TCV

* Exploring drift effects in TCV single-null plasmas with the UEDGE code

* Understanding and suppressing the near Scrape-Oﬀ Layer heat flux feature in inboard-limited plasmas in TCV

* Spectroscopic investigations of divertor detachment in TCV

* Poloidal asymmetry in the narrow heat flux feature in the TCV scrape-off layer

* Overview of the TCV tokamak program: scientific progress and facility upgrades

* Blob properties in full-turbulence simulations of the TCV scrape-off layer

* Results from recent detachment experiments in alternative divertor configurations on TCV

* Numerical study of potential heat flux mitigation effects in the TCV snowflake divertor

* Enhanced (E)over-right-arrow x (B)over-right-arrow drift effects in the TCV snowflake divertor

* X-Point-Position-Dependent Intrinsic Toroidal Rotation in the Edge of TCV

* X-point Position Dependence of Edge Intrinsic Toroidal Rotation on TCV

* Plasma turbulence, suprathermal ion dynamics and code validation on the basic plasma physics device TORPEX

* Impact of a narrow limiter SOL heat flux channel on the ITER first wall panel shaping

* High density experiments in TCV ohmically heated and L-mode plasmas