Publications by Basil Duval | EPFL Graph Search

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For the first time, the JET operation in deuterium-tritium (D-T) plasma, which is scheduled to take place on JET in 2020, will be performed in the ITER mix of plasma-facing component materials. In view of the preparation of the DT campaign (DTE2), several ...

Real-time (RT) disruption prediction (DP) is essential to trigger mitigation actions that avoid irreversible damage to the devices. This paper deals with disruption mitigation alarms and performs the RT implementation of a probabilistic predictor. The RT i ...

The Materials Detritiation Facility has been designed to thermally treat solid non-combustible radioactive waste produced during operations of the Joint European Torus (JET) that is classified as Intermediate Level Waste in the UK due to its tritium invent ...

Fusion performance in tokamaks hinges critically on the efficacy of the edge transport barrier (ETB) in suppressing energy losses. The new concept of 'fingerprints' is introduced to identify the instabilities that cause transport losses in the ETBs of many ...

Detecting disruptions with sufficient anticipation time is essential to undertake any form of remedial strategy, mitigation or avoidance. Traditional predictors based on machine learning techniques can be very performing, if properly optimised, but do not ...

Density limit disruptions have been studied during the current flat-top of TCA. Disruption occurs at two different densities, depending on discharge programming. The highest densities are achieved by a strong influx of neutral gas called 'hard gas puffing'. This allows the plasma density to cross a range which is otherwise unstable and to reach a second region of stability with high internal inductance. When disruption occurs after hard gas puffing, the internal inductance decreases in time, in contrast to

Developments in the real time control hardware on Tokamak à Configuration Variable (TCV) coupled with the flexibility of plasma shaping and electron cyclotron (EC) heating and current drive actuators are opening many opportunities to perform real time expe ...

Research on the Tokamak à Configuration Variable (TCV) addresses a wide range of key questions relevant to ITER and future fusion power plants. Over the past two years, highly productive experimental campaigns have led to major advances across several areas: the ITER baseline scenario; pedestal properties in low-collisionality, peeling-limited conditions; and the development of high-

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, non-inductive regimes. Alternative high-confinement scenarios have likewise received significant attention, with re

Measurements of neutron streaming through penetrations in biological shields are being carried out at JET fusion device by means of thermoluminescence (TL) detectors with the objective to validate the neutronics codes and nuclear data widely applied in ITE ...

Alpha heating experiments in the Tokamak Fusion Test Reactor (TFTR) and in the Joint European Torus (JET) 1997 DTE1 campaign arc reexamined. In TFTR supershots central electron heating of both deuterium only and deuterium-tritium supershots was dominated b ...

The Tokamak Configuration Variable (TCV) tokamak (R = 0.88 m, a < 0.25 m, B < 1.54 T) programme is based on flexible plasma shaping and heating for studies of confinement, transport, control and power exhaust. Recent advances in fully sustained off-axis electron cyclotron current drive (ECCD) scenarios have allowed the creation of plasmas with high bootstrap fraction, steady-state reversed central shear and an electron internal transport barrier. High elongation plasmas, kappa = 2.5, are produced at low nor

In order to better study conventional and alternative divertor configurations, the TCV Tokamak was recently upgraded. In-vessel graphite baffles were installed in the TCV chamber to delimit a separate divertor chamber from the core that required enhanced d ...

The impact of the change of the mass of hydrogen isotopes on the turbulent particle flux is studied. The trapped electron component of the turbulent particle convection induced by collisionality, which is outward in ion temperature gradient turbulence, inc ...

Injection of high-energy neutral beams (NBIs) of hydrogen isotopes is a well-established method for plasma heating, current drive, and diagnosis of magnetic confinement fusion devices, including tokamaks, stellarators and open systems. NBI diagnostics provide essential information for operation, protection, characterization, and optimization of neutral beams, both on test facilities and during plasma experiments. The TCV tokamak is equipped with three neutral beam injectors (NBIs) — two for heating and one

This paper further analyses the EDGE2D-EIRENE simulations presented by Chankin et al (2017 Nucl. Mater. Energy 12 273), of L-mode JET plasmas in vertical-vertical (VV) and Vertical-horizontal (VH) divertor configurations. As expected, the simulated outer d ...

In some JET discharges, type-I edge localised modes (ELMs) are preceded by a class of low-frequency oscillations (Perez et al 2004 Nucl. Fusion 44 609). While in many cases the ELM is triggered during the growth phase of this oscillation, it is also observ ...

The design and operation of future fusion devices relying on H-mode plasmas requires reliable modelling of edge-localized modes (ELMs) for precise prediction of divertor target conditions. An extensive experimental validation of simple analytical predictio ...

Since pioneering the alternative “snowflake”(SF) divertor, TCV research has concentrated on understanding its usefulness and applicability for a fusion reactor. It was first demonstrated that this divertor configuration is compatible with the high confinement H-mode regime on TCV and other machines. Since the main hope for this configuration is to lower the peak power incident on the divertor, and in particular near the strike points, this paper presents a résumé of experiments on TCV that seek to understan

This paper presents the first result using nitrogen-seeded exhaust feedback control of the NII impurity emission front in TCV. The NII emission front position is consistently located below its commonly used CIII counterpart, indicating the NII emission fro ...

Plasma edge simulations with the SOLPS-ITER code are performed to study the influence of divertor baffles on nitrogen-seeded detachment in Tokamak & agrave; Configuration Variable (TCV) single-null, L-mode discharges. Scans of nitrogen seeding rate are con ...

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The software and hardware architecture of the real-time protection of in-vessel components in JET-ILW

Real-time implementation with FPGA-based DAQ system of a probabilistic disruption predictor from scratch

Preparation for commissioning of materials detritiation facility at Culham Science Centre

Gyrokinetic analysis and simulation of pedestals to identify the culprits for energy losses using 'fingerprints'

Adaptive predictors based on probabilistic SVM for real time disruption mitigation on JET

Density Limits and Disruptions in the Tca Tokamak

Real time control of plasmas and ECRH systems on TCV

Progress and innovations in the TCV tokamak research programme

TLD calibration for neutron fluence measurements at JET fusion facility

Alpha heating, isotopic mass, and fast ion effects in deuterium-tritium experiments

An overview of results from the TCV tokamak

Thomson scattering measurements in the divertor region of the TCV Tokamak plasmas

Dependence of the turbulent particle flux on hydrogen isotopes induced by collisionality

Diagnostics for characterization of neutral beams parameters at TCV

Neutral pathways and heat flux widths in vertical- and horizontal-target EDGE2D-EIRENE simulations of JET

Long-lived coupled peeling ballooning modes preceding ELMs on JET

Experimental validation of an analytical kinetic model for edge-localized modes in JET-ITER-like wall

Progress in Snowflake Divertor Studies on TCV

Model-based impurity emission front control using deuterium fueling and nitrogen seeding in TCV

Investigating the influence of divertor baffles on nitrogen-seeded detachment in TCV with SOLPS-ITER simulations and TCV experiments