Publications de Olivier Sauter

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A theoretical model for isotopologues of beryllium monohydride, BeH, BeD and BeT, A (2)Pi to X (2)Sigma(+) visible and X (2)Sigma(+) to X (2)Sigma(+) infrared rovibronic spectra is presented. The MARVEL procedure is used to compute empirical rovibronic ene ...

Electron-scale micro-turbulence driven by the electron temperature gradient (ETG) instability has recently been shown to impact the electron heat transport in tokamaks. Given the relevance of these mechanisms for ITER scenarios, a new study has been carrie ...

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 ...

Strongly-shaped diverted negative triangularity (NT) plasmas in the DIII-D tokamak demonstrate simultaneous access to high normalized density, current, pressure, and confinement. NT plasmas are shown to exist across an expansive parameter space compatible ...

A new paradigm is presented to reconstruct the plasma current density profile in a tokamak in real-time. The traditional method of basing the reconstruction on real-time diagnostics combined with a real-time Grad-Shafranov solver suffers from the difficult ...

An approximate model for a single fluid three-dimensional (3D) magnetohydrodynamic (MHD) equilibrium with pure isothermal toroidal flow with imposed nested magnetic flux surfaces is proposed. It recovers the rigorous toroidal rotation equilibrium description in the axisymmetric limit. The approximation is valid under conditions of nearly rigid or vanishing toroidal rotation in regions with significant 3D deformation of the equilibrium flux surfaces. Bifurcated helical core equilibrium simulations of long-li

The first divertor was installed in the JET machine between 1992 and 1994 and was operated with carbon tiles and then beryllium tiles in 1994-5. Post-mortem studies after these first experiments demonstrated that most of the impurities deposited in the div ...

For some time it has not been clear to what extent neutral injected beam ions have a stabilizing influence on sawteeth. To investigate this, the well known toroidal internal kink instability is generalized to account for weakly anisotropic and flowing equilibria. An analytical approach is proposed, which upon employing an appropriate model distribution function, accurately accounts for the hot ion response of neutral beam injection (NBI) to the internal kink mode. Large fluid contributions, which are expect

A validation of the ITER real-time reconstruction algorithms for the plasma current, centroid position, boundary and for the poloidal beta has been performed using the data collected during the first operation of the JT-60SA tokamak. The accuracy of the reconstruction is evaluated against plasma equilibria computed with the CREATE-NL nonlinear code. As it will be shown, although the setup of the magnetic sensors during JT-60SA first operation included a reduced number of sensors compared to what envisaged i

The role of the current profile and ion and electron temperature ratio in Tokamak A Configuration Variable (TCV) electron internal transport barrier (eITB) noninductive discharges is inspected by means of the linear gyrokinetic global code LORB5 (Bottino e ...

Tungsten (W) melting due to transient power loads, for example those delivered by edge localised modes (ELMs), is a major concern for next step fusion devices. A series of experiments has been performed on JET to investigate the dynamics of Type-I ELM-indu ...

This paper details progress in experimental characterisation work at JET for the long-term irradiation station, conducted as part of a project to perform activation experiments using ITER materials. The aim is to take advantage of the significant 14 MeV ne ...

A model based on the linearized Vlasov-Maxwell equations, taking into account the non-local interactions of particles due to their finite Larmor radii, has been developed. Assuming an inhomogeneous I-D slab plasma, Maxwellian equilibrium distribution functions and k(y) = 0, this model leads to a system of one first-order and two second-order integro-differential equations for E(x) and E(y), E(z), respectively. These equations are valid for arbitrary values of k(perpendicular-to) rho(sigma), where k(perpendi

Beryllium oxide (BeO) and deuteroxide (BeOxDy) have been found on the melted zone of a beryllium tile extracted from the upper dump plate of JET-ILW (2011-2012 campaign). Results have been obtained using Raman microscopy, which is sensitive to both the che ...

The operating space of the TCV tokamak has been extended to higher elongation, kappa = 2.8, and higher normalized current, I-N = I-p/aB = 3.6MA/mT, than were previously attainable. This has been achieved by optimizing the parameters of the vertical position control system and by optimizing the plasma shape. Experimental current and beta limits were found to be consistent with ideal MHD stability calculations, using measured plasma shapes and profiles. The sawtooth period was measured as a function of elonga

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 ...

This study provides a detailed analysis of ion cyclotron resonance heating (ICRH) scenarios for ADITYA-U Tokamak which is a crucial technique for core plasma heating in magnetically confined devices. The ICRH code LION is used to study the cyclotron resona ...

Effect of ELMs on fuel retention at the bulk W target of JET ITER-Like Wall was studied with multi-scale calculations. Plasma input parameters were taken from ELMy H-mode plasma experiment. The energetic intra-ELM fuel particles get implanted and create ne ...

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 ...

The TCV tokamak (B-T < 1.5 T, R approximate to 0.88 m, a < 0.25 m) has produced a wide variety of plasma configurations, both diverted and limited, with elongations kappa(a), ranging from 0.9 to 2.58, triangularities delta(a) from -0.7 to 1 as well as discharges with nearly rectangular cross sections. Plasma currents of 1 MA have been obtained in elongated discharges (kappa(a) approximate to 2.3). Ohmic discharges with delta(a) < 0 have smaller sawteeth and higher levels of MHD mode activity than plasmas wi

Olivier Sauter

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Synthetic spectra of BeH, BeD and BeT for emission modeling in JET plasmas

Investigation of the role of electron temperature gradient modes in electron heat transport in TCV plasmas

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

Simultaneous access to high normalized density, current, pressure, and confinement in strongly-shaped diverted negative triangularity plasmas

Real-time physics-model-based simulation of the current density profile in tokamak plasmas

An approximate single fluid 3-dimensional magnetohydrodynamic equilibrium model with toroidal flow

Material migration and fuel retention studies during the JET carbon divertor campaigns

The internal kink mode in an anisotropic flowing plasma with application to modeling neutral beam injected sawtoothing discharges

Preliminary validation of ITER magnetic diagnostic algorithms by using JT-60SA magnetic measurements

Linear stability analysis of microinstabilities in electron internal transport barrier non-inductive discharges

Heat flux analysis of Type-I ELM impact on a sloped, protruding surface in the JET bulk tungsten divertor

Activation of ITER materials in JET: nuclear characterisation experiments for the long-term irradiation station

Nonlocal Effects of Alpha-Particles on Icrf Heating

Identification of BeO and BeOxDy in melted zones of the JET Be limiter tiles: Raman study using comparison with laboratory samples

Stability and energy confinement of highly elongated plasmas in TCV

The quasi-continuous exhaust regime in ASDEX Upgrade and JET

Study and Analysis of Ion Cyclotron Resonance Heating Scenarios for Aditya-u Tokamak

Modelling of the effect of ELMs on fuel retention at the bulk W divertor of JET

H-Mode density limit disruption avoidance in ASDEX Upgrade, TCV and JET

Effect of plasma shape on confinement and MHD behaviour in TCV