Search Results - "Pégourié, B."
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1
A comparison of the influence of plasmoid-drift mechanisms on plasma fuelling by cryogenic pellets in ITER and Wendelstein 7-X
Published in Nuclear fusion (01-04-2023)“…Abstract Pellet injection is the most promising technique to achieve efficient plasma core fuelling, key for attaining stationary scenarios in large magnetic…”
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Journal Article -
2
Micron-sized dust and nanoparticles produced in the WEST tokamak
Published in Nuclear materials and energy (01-09-2023)“…•Tungsten nanoparticles produced in a tokamak of tungsten divertor.•Micron-sized tungsten dust particles emitted during off normal events.•Helium nanobubbles…”
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3
Separatrix parameters and core performances across the WEST L-mode database
Published in Nuclear fusion (01-05-2023)“…Abstract WEST database analysis shows a correlation of the recycled neutral source around the separatrix with core performances. This observation questions the…”
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4
Raman microscopy to characterize plasma-wall interaction materials: from carbon era to metallic walls
Published in Materials research express (01-10-2023)“…Abstract Plasma-wall interaction in magnetic fusion devices is responsible for wall changes and plasma pollution with major safety issues. It is investigated…”
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5
Numerical modelling of the impact of leakage under divertor baffle in WEST
Published in Nuclear materials and energy (01-10-2022)“…In WEST experimental campaign C5, the divertor pumping capability has been improved by sealing the space between the divertor outer baffle and the vacuum…”
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6
Deuterium and helium outgassing following plasma discharges in WEST: Delayed D outgassing during D-to-He changeover experiments studied with threshold ionization mass spectrometry
Published in Nuclear materials and energy (01-03-2021)“…•New calibration method for threshold ionization mass spectrometry (TIMS) in tokamak.•Uncertainty evaluation of TIMS in plasma discharge and post-discharge.•He…”
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7
Confocal microscopy: A new tool for erosion measurements on large scale plasma facing components in tokamaks
Published in Journal of nuclear materials (01-07-2013)“…A diagnostic based on confocal microscopy was developed at CEA Cadarache in order to measure erosion on large plasma facing components during shutdown in situ…”
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8
Changeover between helium and hydrogen fueled plasmas in JET and WEST
Published in Nuclear materials and energy (01-03-2024)“…•WEST and JET perormed a back-and-forth transition between hydrogen (H) or deuterium (D) and helium (He) plasma operation allowing assessing the achievable…”
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9
Feasibility study of an actively cooled tungsten divertor in Tore Supra for ITER technology testing
Published in Fusion engineering and design (01-10-2011)“…In order to reduce the risks for ITER Plasma Facing Components (PFCs), it is proposed to equip Tore Supra with a full tungsten divertor, benefitting from the…”
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Journal Article Conference Proceeding -
10
Recent results on Ion Cyclotron Wall Conditioning in mid and large size tokamaks
Published in Journal of nuclear materials (01-08-2011)“…Wall conditioning techniques applicable in the presence of permanent toroidal magnetic field will be required for the operation of ITER, in particular for…”
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Journal Article Conference Proceeding -
11
Overview of the deuterium inventory campaign in Tore Supra: Operational conditions and particle balance
Published in Journal of nuclear materials (15-06-2009)“…A specific experiment was performed in Tore Supra, dedicated to the search for consistency between wall inventories estimated from gas balance and post-mortem…”
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Journal Article Conference Proceeding -
12
Raman study of CFC tiles extracted from the toroidal pump limiter of Tore Supra
Published in Journal of nuclear materials (01-08-2011)“…The structure of six tiles extracted from the erosion and deposition zones (thin and thick deposition) of the Tore Supra toroidal pump limiter (TPL) have been…”
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Journal Article Conference Proceeding -
13
Bifurcation to a stable limiter MARFE in Tore Supra
Published in Journal of nuclear materials (01-07-2013)“…This paper reports on the observation on the tokamak Tore Supra of a very high density, highly radiating edge regime featuring a high recycling divertor. This…”
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14
Carbon dust formation in a cold plasma from cathode sputtering
Published in Journal of nuclear materials (15-06-2009)“…Nanoparticles are produced in argon glow plasmas where carbon is introduced by sputtering of a graphite cathode. A scaling law of growth is reported on as a…”
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Journal Article Conference Proceeding -
15
Dynamic modelling of local fuel inventory and desorption in the whole tokamak vacuum vessel for auto-consistent plasma-wall interaction simulations
Published in Nuclear materials and energy (01-05-2019)“…•A model to simulate the dynamic thermal desorption of hydrogen isotopes is built for the SolEdge2D-EIRENE code package.•This model is used for simulating a…”
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16
Physico-chemical characteristics of carbon deposits collected in TEXTOR and Tore Supra tokamaks
Published in Carbon (New York) (01-11-2007)“…For safety reasons, the formation of carbon deposits in tokamaks must be limited. To understand how these deposits are formed, a comparative study of the…”
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17
Deuterium inventory in Tore Supra: Coupled carbon–deuterium balance
Published in Journal of nuclear materials (01-07-2013)“…This paper presents an analysis of the carbon–deuterium circulation and the resulting balance in Tore Supra over the period 2002–2007. Carbon balance combines…”
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18
Multi machine scaling of fuel retention in 4 carbon dominated tokamaks
Published in Journal of nuclear materials (01-08-2011)“…In order to benchmark predictions for the in vessel tritium inventory in ITER, a survey of fuel retention measured in 4 carbon dominated tokamaks (TEXTOR,…”
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Journal Article Conference Proceeding -
19
Structure of pellet cloud emission and relation with the local ablation rate
Published in Nuclear fusion (01-05-2024)“…Abstract The experimental reproduction of the conditions of pellet injection expected in future large devices being not possible in present day machines, it is…”
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Journal Article -
20
Proposal of a control scheme for testing a centrifuge-based pellet injection system in DIPAK-PET
Published in Fusion engineering and design (01-02-2024)“…The envisaged Pellet Engineering Testbed (PET) in the framework of Direct Internal Recycling Integrated Development Platform Karlsruhe (DIPAK) will provide…”
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