L. Delpech
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View article: A Population’s Perception of the Risk Management-Driven Response during Major Landslides
A Population’s Perception of the Risk Management-Driven Response during Major Landslides Open
The Saguenay region in Quebec has experienced several major disasters over the past few decades, namely, the Saint-Jean-Vianney landslide in 1971 and the Saguenay Flood in 1996, as well as several frequently publicized terrain instability …
View article: Impact of lower hybrid current drive on edge velocity shear and turbulence in the HL-2A tokamak
Impact of lower hybrid current drive on edge velocity shear and turbulence in the HL-2A tokamak Open
The effect of lower hybrid current drive (LHCD) on edge velocity shear and turbulence in the HL-2A tokamak has been investigated. Experimental results demonstrate that the LHCD leads to an increase in edge velocity shear at both the inner …
View article: WEST full tungsten operation with an ITER grade divertor
WEST full tungsten operation with an ITER grade divertor Open
The mission of WEST (tungsten-W Environment in Steady-state Tokamak) is to explore long pulse operation in a full tungsten (W) environment for preparing next-step fusion devices (ITER and DEMO) with a focus on testing the ITER actively coo…
View article: First lower hybrid current drive experiments on the WEST tokamak
First lower hybrid current drive experiments on the WEST tokamak Open
The first lower hybrid current drive experiments in the full tungsten WEST tokamak are reported. Good wave coupling is found at rather low plasma current (q95~4.3) and medium density (ne~3×1019m-3). Reflection coefficient is in agreement w…
View article: Operational domain for the new 3MW/1000s ECRH System on WEST
Operational domain for the new 3MW/1000s ECRH System on WEST Open
The ECRH system formerly used in Tore Supra is being upgraded to start on WEST in 2023, at a power level of 1MW and frequency of 105 GHz. Its ultimate 3MW/1000s capability is expected to enlarge the WEST operational domain by increasing ma…
View article: Developing high performance RF heating scenarios on the WEST tokamak
Developing high performance RF heating scenarios on the WEST tokamak Open
High power experiments, up to 9.2 MW with LHCD and ICRH, have been carried out in the full tungsten tokamak WEST. Quasi non inductive discharges have been achieved allowing to extend the plasma duration to 53 s with stationary conditions i…
View article: Improvement of lower hybrid current drive systems for high-power and long-pulse operation on EAST
Improvement of lower hybrid current drive systems for high-power and long-pulse operation on EAST Open
International audience
View article: Developing high performance RF heating scenarios on the WEST tokamak
Developing high performance RF heating scenarios on the WEST tokamak Open
High power experiments, up to 9.2 MW with LHCD and ICRH, have been carried out in the full tungsten tokamak WEST. Quasi non inductive discharges have been achieved allowing to extend the plasma duration to 53s with stationary conditions in…
View article: Progress of HL-2A experiments and HL-2M program
Progress of HL-2A experiments and HL-2M program Open
Since the last IAEA Fusion Energy Conference in 2018, significant progress of the experimental program of HL-2A has been achieved on developing advanced plasma physics, edge localized mode (ELM) control physics and technology. Optimization…
View article: Sustained W-melting experiments on actively cooled ITER-like plasma facing unit in WEST
Sustained W-melting experiments on actively cooled ITER-like plasma facing unit in WEST Open
The consequences of tungsten (W) melting on divertor lifetime and plasma operation are high priority issues for ITER. Sustained and controlled W-melting experiment has been achieved for the first time in WEST on a poloidal sharp leading ed…
View article: Investigation of plasma wall interactions between tungsten plasma facing components and helium plasmas in the WEST tokamak
Investigation of plasma wall interactions between tungsten plasma facing components and helium plasmas in the WEST tokamak Open
ITER will operate with a tungsten divertor, a material featuring surface morphology changes when exposed to helium plasmas, in particular the formation of the so called tungsten fuzz under specific conditions. Investigating interactions be…
View article: Operating a full tungsten actively cooled tokamak: overview of WEST first phase of operation
Operating a full tungsten actively cooled tokamak: overview of WEST first phase of operation Open
WEST is an MA class superconducting, actively cooled, full tungsten (W) tokamak, designed to operate in long pulses up to 1000 s. In support of ITER operation and DEMO conceptual activities, key missions of WEST are: (i) qualification of h…
View article: Long discharges in a steady state with D<sub>2</sub> and N<sub>2</sub> on the actively cooled tungsten upper divertor in WEST
Long discharges in a steady state with D<sub>2</sub> and N<sub>2</sub> on the actively cooled tungsten upper divertor in WEST Open
International audience
View article: Coupling properties of the LHCD launchers in the WEST experiments
Coupling properties of the LHCD launchers in the WEST experiments Open
The aim of WEST [1] [2] is to master long pulses (> 30s and up to 1000s) and submit ITER like tungsten divertor tiles to power fluxes of 10 MW/m2. To reach these goals, the Tore Supra Lower Hybrid Current Drive system (LHCD) constituted by…
View article: Recent LHCD experiments on HL-2A and LHCD system development on HL-2M
Recent LHCD experiments on HL-2A and LHCD system development on HL-2M Open
This paper presents recent Lower Hybrid Current Drive (LHCD) progress in SWIP, including the experiments on HL-2A and system development on HL-2M. The 3.7GHz LHCD system was built on HL-2A, where the first Lower Hybrid Wave (LHW) coupling …
View article: First lower hybrid current drive experiments on the WEST tokamak
First lower hybrid current drive experiments on the WEST tokamak Open
The first lower hybrid current drive experiments in the full tungsten WEST tokamak are reported. Good wave coupling is found at rather low plasma current (q95∼4.3) and medium density (ne∼3×1019m-3). Reflection coefficient is in agreement w…
View article: Measurements of the fast electron bremsstrahlung during lower hybrid current drive in the HL-2A tokamak
Measurements of the fast electron bremsstrahlung during lower hybrid current drive in the HL-2A tokamak Open
Physics related to fast electrons in lower hybrid (LH) current drive (LHCD) plasma is a very important issue, since these particles will play an important role in runaway electron (RE) generation and lower hybrid wave (LHW)-related physics…
View article: Ramping up RF power and increasing pulse length in the full tungsten environment of WEST
Ramping up RF power and increasing pulse length in the full tungsten environment of WEST Open
International audience
View article: Development and Application of 3.7GHz LHCD system on HL-2A and Development of RF Heating system on HL-2M
Development and Application of 3.7GHz LHCD system on HL-2A and Development of RF Heating system on HL-2M Open
\nThe first Lower Hybrid (LH) experiments were carried out with a Passive-Active Multijunction (PAM) launcher in H-mode plasmas. The experiments were performed on the HL-2A tokamak with the new 3.7 GHz LHCD system, installed and tested by …
View article: Maintenance and preparation of the 3.7 GHz LHCD system for WEST operation
Maintenance and preparation of the 3.7 GHz LHCD system for WEST operation Open
\nThe generator for the 3.7 GHz Lower Hybrid Current Drive (LHCD) system on Tore Supra consists of 16 klystrons capable of delivering 600kW/1000s each on plasma. Such a powerful installation needs to be operated on a regular basis in order…