Publications de Olivier Sauter

Milestone in predicting core plasma turbulence: successful multi-channel validation of the gyrokinetic code GENE

Olivier Sauter, Basil Duval, Stefano Coda, Timothy Goodman, Benoît Labit, Alessandro Pau, Federico Alberto Alfredo Felici, Cristian Sommariva, Laurie Porte, Antoine Pierre Emmanuel Alexis Merle

On the basis of several recent breakthroughs in fusion research, many activities have been launched around the world to develop fusion power plants on the fastest possible time scale. In this context, high-fidelity simulations of the plasma behavior on lar ...

2025

Overview of the third JET deuterium-tritium campaign

Olivier Sauter, Holger Reimerdes, Benoît Labit

JET returned to deuterium-tritium operations in 2023 (DTE3 campaign), approximately two years after DTE2. DTE3 was designed as an extension of JET’s 2022-2023 deuterium campaigns, which focused on developing scenarios for ITER and DEMO, integrating in-dept ...

2025

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

Olivier Sauter, Francesco Pastore

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 ...

Elsevier BV2025

The quasi-continuous exhaust regime in ASDEX Upgrade and JET

Olivier Sauter, Benoît Labit

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 ...

Elsevier2025

Design and implementation of a model-based hierarchical architecture for plasma shape control in the TCV tokamak

Olivier Sauter, Stefano Coda, Federico Alberto Alfredo Felici, Antoine Pierre Emmanuel Alexis Merle, Cristian Galperti

Plasma shape control is a fundamental tool for effective tokamak operation, allowing improved plasma performance and the pursuit of challenging scientific objectives. In this framework, the Tokamak á Configuration Variable (TCV) of the École Polytechnique ...

IOP Publishing2025

Lessons Learned Executing the Non-disruptive Compass Scan Method at Jet Towards Error Field Identification Experiments in Iter

Olivier Sauter, Alessandro Pau

In preparation for error field (EF) identification experiments in ITER, a series of experiments have been conducted at JET to test the portability of the non-disruptive compass scan, a method originally designed and tested in DIII-D (Paz-Soldan et al 2022 ...

IOP Publishing Ltd2025

Impact of the Plasma Boundary on Machine Operation and the Risk Mitigation Strategy on Jet

Olivier Sauter, Benoît Labit

This work examines the separatrix and Scrape-off-Layer (SOL) characteristics in three scenarios on JET: the Quasi-Continuous Exhaust (QCE) regime, the ITER Baseline scenario, and the X-point Radiator (XPR) regime. All three scenarios are potentially compat ...

IOP Publishing Ltd2025

Plasma state monitoring and disruption characterization using multimodal VAEs

Olivier Sauter, Alessandro Pau

When a plasma disrupts in a tokamak, significant heat and electromagnetic loads are deposited onto the surrounding device components. These forces scale with plasma current and magnetic field strength, making disruptions one of the key challenges for futur ...

2025

Operation Above the Greenwald Density Limit in High Performance DIII-d Negative Triangularity Discharges

Olivier Sauter

The density limit in strongly-shaped negative triangularity (NT) discharges is studied experimentally in the DIII-D tokamak. Record-high Greenwald fractions fG are obtained, using gas puff injection only, with values up to near 2, where fG is defined as th ...

IOP Publishing Ltd2025

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

Olivier Sauter

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 ...

IOP Publishing Ltd2025