Mehdi Firdaouss

84
Documents
Affiliation actuelle
  • Institut de Recherche sur la Fusion par confinement Magnétique (IRFM)

Domaines de recherche

Mécanique des matériaux [physics.class-ph] Sciences de l'ingénieur [physics]

Publications

Publications

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High heat flux testing of actively cooled graphite- and tungsten-armoured JT-60SA flat tile divertor mock-ups

Daniel Dickes , Bernd Böswirth , Katja Hunger , Gabriel Peyron , Quentin Tichit et al.

Nuclear Materials and Energy, 2026, 46, pp.102067. ⟨10.1016/j.nme.2026.102067⟩

Article dans une revue cea-05478015v1

Divertor shaping with neutral baffling as a solution to the tokamak power exhaust challenge

Kevin Verhaegh , James Harrison , David Moulton , Bruce Lipschultz , Nicola Lonigro et al.

Communications Physics, 2025, 8 (1), pp.215. ⟨10.1038/s42005-025-02121-1⟩

Article dans une revue hal-05282872v1
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Demonstration of Super-X divertor exhaust control for transient heat load management in compact fusion reactors

B. Kool , K. Verhaegh , G. Derks , T. Wijkamp , J. Koenders et al.

Nature Energy, 2025, ⟨10.1038/s41560-025-01824-7⟩

Article dans une revue hal-05282776v1
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Thermal and structural analysis of JT-60SA actively cooled divertor target submitted to high heat flux

S. Garitta , T. Batal , A. Durif , M. Firdaouss , M. Missirlian et al.

Fusion Engineering and Design, 2024, 199, pp.114133. ⟨10.1016/j.fusengdes.2023.114133⟩

Article dans une revue cea-04748693v1
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Designing tungsten armoured plasma facing components to pulsed heat loads in magnetic fusion machines

R Mitteau , M Diez , M Firdaouss

Nuclear Materials and Energy, 2024, 41, pp.101777. ⟨10.1016/j.nme.2024.101777⟩

Article dans une revue cea-04739158v1
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Development of Boron Coatings for antenna protection limiters in the WEST Tokamak

C. Hernandez , M. Firdaouss , A. Deleau , M. Diez , Marc Missirlian

Nuclear Materials and Energy, 2024, 38, pp.101573. ⟨10.1016/j.nme.2023.101573⟩

Article dans une revue cea-04590200v1
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WEST full tungsten operation with an ITER grade divertor

J. Bucalossi , A. Ekedahl , J. Achard , K. Afonin , O. Agullo et al.

Nuclear Fusion, 2024, 64 (11), pp.112022. ⟨10.1088/1741-4326/ad64e5⟩

Article dans une revue hal-04948518v1
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Evolution and cleaning of the deposit layers on the lower divertor of WEST fully equipped with ITER grade components

J. Gerardin , Y. Corre , C. Desgranges , M. Diez , L. Dubus et al.

Nuclear Materials and Energy, 2024, 41, pp.101783. ⟨10.1016/j.nme.2024.101783⟩

Article dans une revue cea-04816503v1
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Overview of the EUROfusion Tokamak Exploitation programme in support of ITER and DEMO

E. Joffrin , M. Wischmeier , M. Baruzzo , A. Hakola , A. Kappatou et al.

Nuclear Fusion, 2024, 64 (11), pp.112019. ⟨10.1088/1741-4326/ad2be4⟩

Article dans une revue hal-04850452v1
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Testing of ITER-grade plasma facing units in the WEST tokamak: Progress in understanding heat loading and damage mechanisms

Y. Corre , M-H. Aumeunier , A. Durif , J. Gaspar , K. Krieger et al.

Nuclear Materials and Energy, 2023, 37, pp.101546. ⟨10.1016/j.nme.2023.101546⟩

Article dans une revue hal-04396244v1
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Plasma exposure of a pre-damaged ITER-like plasma facing unit in the WEST tokamak: in-situ and post-mortem measurements

Yann Corre , Torsten Loewenhoff , Marianne Richou , Sebastijan Brezinsek , Jan Coenen et al.

Nuclear Materials and Energy, 2023, 34, pp.101366. ⟨10.1016/j.nme.2023.101366⟩

Article dans une revue hal-04396238v1
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Manufacturing, testing and installation of the full tungsten actively cooled ITER-like divertor in the WEST tokamak

Marc Missirlian , M. Firdaouss , Marianne Richou , C. Hernandez , L Gargiulo et al.

Fusion Engineering and Design, 2023, 193, pp.113683. ⟨10.1016/j.fusengdes.2023.113683⟩

Article dans une revue cea-04619420v1
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Overview of plasma-tungsten surfaces interactions on the divertor test sector in WEST during the C3 and C4 campaigns

M. Diez , M. Balden , S. Brezinsek , Y. Corre , N. Fedorczak et al.

Nuclear Materials and Energy, 2023, 34, pp.101399. ⟨10.1016/j.nme.2023.101399⟩

Article dans une revue hal-04396242v1
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Infrared detection of tungsten cracking on actively cooled ITER-like component during high power experiment in WEST

Q. Tichit , A. Durif , J. Gaspar , Y. Anquetin , Y. Corre et al.

Nuclear Materials and Energy, 2023, 37, pp.101537. ⟨10.1016/j.nme.2023.101537⟩

Article dans une revue hal-04396240v1

Electromagnetic modeling for JT-60SA divertor HHF OVT C target

S. Garitta , T. Batal , M. Firdaouss , M. Richou , P. Testoni et al.

Fusion Engineering and Design, 2023, 187, pp.113400. ⟨10.1016/j.fusengdes.2022.113400⟩

Article dans une revue cea-04765165v1
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Operating a full tungsten actively cooled tokamak: overview of WEST first phase of operation

J. Bucalossi , J. Achard , O. Agullo , T. Alarcon , L. Allegretti et al.

Nuclear Fusion, 2022, 62 (4), pp.042007. ⟨10.1088/1741-4326/ac2525⟩

Article dans une revue hal-03741642v1

First plasma exposure of a pre-damaged ITER-like plasma-facing unit in the WEST tokamak: procedure for the PFU preparation and lessons learned

Marianne Richou , Yann Corre , Thorsten Loewenhoff , Mathilde Diez , Céline Martin et al.

Nuclear Fusion, 2022, 62 (5), pp.056010. ⟨10.1088/1741-4326/ac412e⟩

Article dans une revue cea-04765195v1
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Integrated design strategy for EU-DEMO first wall protection from plasma transients

Francesco Maviglia , Christian Bachmann , Gianfranco Federici , Thomas Franke , Mattia Siccinio et al.

Fusion Engineering and Design, 2022, 177, pp.113067. ⟨10.1016/j.fusengdes.2022.113067⟩

Article dans une revue cea-04765269v1
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Overview of the emissivity measurements performed in WEST: in-situ and post-mortem observations

J. Gaspar , Y. Corre , F. Rigollet , M.-H. Aumeunier , E. Bernard et al.

Nuclear Fusion, 2022, 62 (9), pp.096023. ⟨10.1088/1741-4326/ac6f68⟩

Article dans une revue hal-04029656v1
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Status of the WEST travelling wave array antenna design and results from the high power mock-up

R. Ragona , F. Durodié , A. Messiaen , J. Ongena , M. van Schoor et al.

Nuclear Fusion, 2022, 62 (2), pp.026046. ⟨10.1088/1741-4326/ac4467⟩

Article dans une revue cea-03533314v1
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Emissivity measurement of the ITER-like plasma facing components of the WEST phase 2: Pre-exposure measurements and first WEST exposure

J. Gaspar , F. Rigollet , N. Ehret , Y. Anquetin , E. Bernard et al.

Nuclear Materials and Energy, 2022, 33, pp.101305. ⟨10.1016/j.nme.2022.101305⟩

Article dans une revue hal-04029665v1
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Integrated design strategy for EU-DEMO first wall protection from plasma transients Fusion Engineering and Design 177 (2022) 113067

Francesco Maviglia , Christian Bachmann , Gianfranco Federici , Thomas Franke , Mattia Siccinio et al.

Fusion Engineering and Design, 2022, 178, pp.113125. ⟨10.1016/j.fusengdes.2022.113125⟩

Article dans une revue cea-04765260v1

Modelling of the complete heat flux deposition on the CFETR first wall with neon seeding

Feifei Nian , Zhongshi Yang , Rui Ding , Jingbo Chen , Guojian Niu et al.

Plasma Physics and Controlled Fusion, 2021, 63 (9), pp.095004. ⟨10.1088/1361-6587/ac0a3d⟩

Article dans une revue cea-04765278v1
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Sustained W-melting experiments on actively cooled ITER-like Plasma Facing Unit in WEST

Yann Corre , Alex Grosjean , James P. Gunn , Karl Krieger , Svetlana Ratynskaia et al.

Physica Scripta, 2021, 96 (12), pp.124057. ⟨10.1088/1402-4896/ac326a⟩

Article dans une revue hal-03583706v1
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Divertor power loads and scrape off layer width in the large aspect ratio full tungsten tokamak WEST

J. Gaspar , Yann Corre , Nicolas Fedorczak , J.P. Gunn , Clarisse Bourdelle et al.

Nuclear Fusion, 2021, 61 (9), pp.096027. ⟨10.1088/1741-4326/ac1803⟩

Article dans une revue cea-03345900v1
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First temperature database achieved with Fiber Bragg Grating sensors in uncooled plasma facing components of the WEST lower divertor

Y Corre , N Chanet , Romain Cotillard , J Gaspar , Guillaume Laffont et al.

Fusion Engineering and Design, 2021, 170, pp.112528. ⟨10.1016/j.fusengdes.2021.112528⟩

Article dans une revue hal-03583708v1
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Sustained W-melting experiments on actively cooled ITER-like Plasma Facing Unit in WEST

Yann Corre , A Grosjean , J Gunn , K Krieger , S Ratynskaia et al.

Physica Scripta, 2021

Article dans une revue hal-03652668v1
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Very high-resolution infrared imagery of misaligned tungsten monoblock edge heating in the WEST tokamak

A Grosjean , Y Corre , J Gaspar , J P Gunn , S Carpentier et al.

Nuclear Materials and Energy, 2021, 27, ⟨10.1016/j.nme.2021.100910⟩

Article dans une revue hal-03578420v1
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First feedback during series fabrication of ITER like divertor tungsten components for the WEST tokamak

M Firdaouss , Q Li , M Lipa , G Luo , M Missirlian et al.

Physica Scripta, 2021, 96 (12), pp.124037. ⟨10.1088/1402-4896/ac2978⟩

Article dans une revue cea-04746485v1

Acceptance tests of the industrial series manufacturing of WEST ITER-like tungsten actively cooled divertor

Marianne Richou , Marc Missirlian , Mehdi Firdaouss , Bernd Böswirth , Mathilde Diez et al.

Physica Scripta, 2021, 96 (12), pp.124029. ⟨10.1088/1402-4896/ac2657⟩

Article dans une revue hal-04768143v1
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Thermal loads in gaps between ITER divertor monoblocks: first lessons learnt from WEST

J.P. Gunn , J. Bucalossi , Y. Corre , M. Diez , E. Delmas et al.

Nuclear Materials and Energy, 2021, 27, pp.100920. ⟨10.1016/j.nme.2021.100920⟩

Article dans une revue cea-03202595v1
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Interpretation of temperature distribution observed on W-ITER-like PFUs in WEST monitored with a very-high-resolution IR system

A Grosjean , M H Aumeunier , Y Corre , M Firdaouss , J Gaspar et al.

Fusion Engineering and Design, 2021, 168, pp.112387. ⟨10.1016/j.fusengdes.2021.112387⟩

Article dans une revue hal-03578445v1
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In situ observation of tungsten plasma-facing components after the first phase of operation of the WEST tokamak

M. Diez , Y. Corre , E. Delmas , N. Fedorczak , M. Firdaouss et al.

Nuclear Fusion, 2021, 61 (10), pp.106011. ⟨10.1088/1741-4326/ac1dc6⟩

Article dans une revue cea-04746758v1
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Erosion and redeposition patterns on entire erosion marker tiles after exposure in the first operation phase of WEST

M Balden , M Mayer , B Bliewert , E Bernard , M Diez et al.

Physica Scripta, 2021, 96 (12), pp.124020. ⟨10.1088/1402-4896/ac2182⟩

Article dans une revue hal-03550892v1
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First analysis of the misaligned leading edges of ITER-like Plasma Facing Units using a very high resolution infrared camera in WEST

A Grosjean , Y Corre , R Dejarnac , J Gaspar , J P Gunn et al.

Nuclear Fusion, 2020

Article dans une revue hal-03148253v1
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Infra-red thermography estimate of deposited heat load dynamics on the lower tungsten divertor of WEST

N Fedorczak , J Gaspar , M Firdaouss , V Moncada , A Grosjean et al.

Physica Scripta, 2020, T171, pp.014046. ⟨10.1088/1402-4896/ab4e3d⟩

Article dans une revue hal-03147419v1
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Design and manufacturing of bulk tungsten tiles for WEST outer limiter

M. Firdaouss , P. Chappuis , S. Gazzotti , M. Lipa , C. Portafaix et al.

Fusion Engineering and Design, 2020, 160, pp.112000. ⟨10.1016/j.fusengdes.2020.112000⟩

Article dans une revue hal-03491201v1

The influence of N on the D retention within W coatings for fusion applications

E. Grigore , M. Gherendi , F. Baiasu , M. Firdaouss , Caroline Hernandez et al.

Fusion Engineering and Design, 2019, 146, pp.1959-1962. ⟨10.1016/j.fusengdes.2019.03.075⟩

Article dans une revue hal-05021064v1

Manufacturing and characterization of stainless steel/CuCrZr and stainless steel/Cu junction ring by explosive welding method

M. Firdaouss , M. Diez , F. Samaille

Fusion Engineering and Design, 2019, 146, pp.1157-1161. ⟨10.1016/j.fusengdes.2019.02.031⟩

Article dans une revue cea-05194310v1
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First heat flux estimation in the lower divertor of WEST with embedded thermal measurements

J. Gaspar , Y. Corre , M. Firdaouss , J.L. Gardarein , J. Gerardin et al.

Fusion Engineering and Design, 2019, 146 part A, pp.757-760. ⟨10.1016/j.fusengdes.2019.01.074⟩

Article dans une revue hal-02050673v1

Investigation of the He content within W coatings by using glow discharge optical emission spectrometry

Caroline Hernandez , Edi Grigore , C. Ruset , M. Firdaouss , M. Gherendi

Romanian Reports in Physics, 2019, 71 (2), pp.1221-1451

Article dans une revue hal-05021382v1
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Tungsten coatings repair: An approach to increase the lifetime of plasma facing components

Mathilde Diez , Mehdi Firdaouss , Marianne Richou , Arnaud Bultel , Frédéric Perry et al.

Fusion Engineering and Design, 2019, 146, pp.800-804. ⟨10.1016/j.fusengdes.2019.01.084⟩

Article dans une revue hal-02110735v1
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Simplified heat load modeling for design of DEMO discrete limiter

J. Gerardin , M. Firdaouss , F. Maviglia , W. Arter , T. Barrett et al.

Nuclear Materials and Energy, 2019, 20, pp.100568. ⟨10.1016/j.nme.2019.01.002⟩

Article dans une revue hal-02190872v1

Calibration procedures of the Tore-Supra infrared endoscopes

C. Desgranges , M. Jouve , C. Balorin , R. Reichle , M. Firdaouss et al.

Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 2018, 879, pp.121-133. ⟨10.1016/j.nima.2017.09.035⟩

Article dans une revue hal-02080913v1
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Heat flux analysis of Type I ELM impact on a sloped, protruding surface in the JET bulk tungsten divertor

J. Gaspar , J. W Coenen , Y. Corre , R. Dejarnac , M. Firdaouss et al.

Nuclear Materials and Energy, 2018, 17, pp.182-187. ⟨10.1016/j.nme.2018.10.009⟩

Article dans une revue hal-02184439v1
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Integration of fiber Bragg grating temperature sensors in plasma facing components of the WEST tokamak

Yann Corre , Guillaume Laffont , Christine Pocheau , Romain Cotillard , Jonathan Gaspar et al.

Review of Scientific Instruments, 2018, 89 (6), pp.063508. ⟨10.1063/1.5024514⟩

Article dans une revue hal-02011117v1
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Surface heat flux estimation with embedded fiber Bragg gratings measurements: Numerical study

J. Gaspar , Y. Corre , J-L. Gardarein , M. Firdaouss , D. Guilhem et al.

Nuclear Materials and Energy, 2017, 12, pp.1077 - 1081. ⟨10.1016/j.nme.2016.10.015⟩

Article dans une revue hal-01794290v1
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Surface heat loads on the ITER divertor vertical targets

J.P. Gunn , S. Carpentier-Chouchana , F. Escourbiac , T. Hirai , S. Panayotis et al.

Nuclear Fusion, 2017, 57 (4), pp.046025. ⟨10.1088/1741-4326/aa5e2a⟩

Article dans une revue cea-04748589v1
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Efficient generation of energetic ions in multi-ion plasmas by radio-frequency heating

O. Kazakov , J. Ongena , E. Lerche , M. Mantsinen , D. Van eester et al.

Nature Physics, 2017, 13 (10), pp.973-978. ⟨10.1038/NPHYS4167⟩

Article dans une revue cea-01898634v1

The DEMO wall load challenge

R. Wenninger , R. Albanese , R. Ambrosino , F. Arbeiter , J. Aubert et al.

Nuclear Fusion, 2017, 57 (4), pp.046002. ⟨10.1088/1741-4326/aa4fb4⟩

Article dans une revue hal-03986061v1

Overview of the different processes of tungsten coating implemented into WEST tokamak

M. Firdaouss , C. Desgranges , C. Hernandez , M. Richou , H. Greuner et al.

Fusion Engineering and Design, 2017, 124, pp.207 - 210. ⟨10.1016/j.fusengdes.2017.02.087⟩

Article dans une revue cea-04747908v1

Overview of the different processes of tungsten coating implemented into WEST tokamak

M. Firdaouss , C. Desgranges , Caroline Hernandez , M. Richou , H. Greuner et al.

Fusion Engineering and Design, 2017, 124, pp.207-210. ⟨10.1016/j.fusengdes.2017.02.087⟩

Article dans une revue hal-05021116v1
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Tungsten coating by ATC plasma spraying on CFC for WEST tokamak

M Firdaouss , C Desgranges , C Hernandez , C Mateus , H Maier et al.

Physica Scripta, 2017, T170, pp.014008. ⟨10.1088/1402-4896/aa8785⟩

Article dans une revue cea-04748755v1

Thermomechanical simulation of WEST actively cooled upper divertor

T. Batal , M. Richou , D. Guilhem , M. Firdaouss , S. Larroque et al.

Fusion Engineering and Design, 2016, 112, pp.36 - 41. ⟨10.1016/j.fusengdes.2016.07.004⟩

Article dans une revue istex cea-04748752v1

Tungsten covered graphite and copper elements and ITER-like actively cooled tungsten divertor plasma facing units for the WEST project

D Guilhem , J Bucalossi , S Burles , Y Corre , F Ferlay et al.

Physica Scripta, 2016, T167, pp.014066. ⟨10.1088/0031-8949/t167/1/014066⟩

Article dans une revue cea-04748773v1

Tungsten coatings for application in WEST project

E. Grigore , M. Gherendi , Caroline Hernandez , C. Desgranges , M. Firdaouss

Nuclear Materials and Energy, 2016, 9, pp.137-140. ⟨10.1016/j.nme.2016.09.003⟩

Article dans une revue hal-05021015v1

Study of the pores inside tungsten coating after thermal cycling for fusion device

C. Desgranges , M. Firdaouss , C. Hernandez , C. Martin , C. Ruset et al.

Physica Scripta, 2016, T167, ⟨10.1088/0031-8949/T167/1/014060⟩

Article dans une revue hal-01455190v1

Evaluation of peak power flux densities based on full ion orbit calculation: Application to WEST ITER-like target

P. Languille , J. P. Gunn , Y. Corre , V. Moncada , J. Bucalossi et al.

Fusion Engineering and Design, 2016, 112, pp.1-6. ⟨10.1016/j.fusengdes.2016.07.002⟩

Article dans une revue istex hal-01455195v1

The WEST project: validation program for WEST tungsten coated plasma facing components

M Richou , M Missirlian , E Tsitrone , J Bucalossi , C Desgranges et al.

Physica Scripta, 2016, T167, pp.014029. ⟨10.1088/0031-8949/t167/1/014029⟩

Article dans une revue cea-04748681v1
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A fatigue lifetime assessment of WEST ITER Like Plasma Facing Unit

P. Languille , Marc Missirlian , D. Guilhem , F. Ferlay , T. Batal et al.

Fusion Engineering and Design, 2016, 109-111, pp.294-298. ⟨10.1016/j.fusengdes.2016.03.009⟩

Article dans une revue cea-04723407v1

Operational limits on WEST inertial divertor sector during the early phase experiment

M Firdaouss , Y Corre , P Languille , H Greuner , E Autissier et al.

Physica Scripta, 2016, T167, pp.014012. ⟨10.1088/0031-8949/2016/t167/014012⟩

Article dans une revue cea-04747892v1

WEST Physics Basis

C. Bourdelle , J.F. Artaud , Vincent Basiuk , M. Bécoulet , S. Brémond et al.

Nuclear Fusion, 2015, 55 (6), pp.063017. ⟨10.1088/0029-5515/55/6/063017⟩

Article dans une revue hal-01550957v1

Design and preliminary thermal validation of the WEST actively cooled upper divertor

M. Richou , M. Missirlian , D. Guilhem , M. Lipa , P. Languille et al.

Fusion Engineering and Design, 2015, 98-99, pp.1394 - 1398. ⟨10.1016/j.fusengdes.2014.12.017⟩

Article dans une revue istex cea-04738409v1
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Plasma facing components integration studies for the WEST divertor

Fabien Ferlay , Marc Missirlian , Dominique Guilhem , Mehdi Firdaouss , Marianne Richou et al.

Fusion Engineering and Design, 2015, 98-99, pp.1285 - 1289. ⟨10.1016/j.fusengdes.2015.02.053⟩

Article dans une revue cea-04747936v1

Heat flux decay length during RF power operation in the Tore Supra tokamak

Y. Corre , J. P. Gunn , M. Firdaouss , S. Carpentier , M. Chantant et al.

Nuclear Fusion, 2014, 54 (1), ⟨10.1088/0029-5515/54/1/013013⟩

Article dans une revue hal-01459438v1

The WEST project: Testing ITER divertor high heat flux component technology in a steady state tokamak environment

J. Bucalossi , M. Missirlian , P. Moreau , F. Samaille , E. Tsitrone et al.

Fusion Engineering and Design, 2014, 89 (7-8), pp.907 - 912. ⟨10.1016/j.fusengdes.2014.01.062⟩

Article dans une revue istex cea-04748647v1

Power handling of the JET ITER-like wall

G. Arnoux , I. Balboa , M. Clever , Stéphane Devaux , P. de Vries et al.

Physica Scripta, 2014, T159, ⟨10.1088/0031-8949/2014/T159/014009⟩

Article dans une revue hal-01286877v1
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The WEST project: Current status of the ITER-like tungsten divertor

Marc Missirlian , J. Bucalossi , Y. Corre , F. Ferlay , M. Firdaouss et al.

Fusion Engineering and Design, 2014, 89 (7-8), pp.1048-1053. ⟨10.1016/j.fusengdes.2014.01.050⟩

Article dans une revue hal-04724821v1

Status of the ITER Ion Cyclotron H&CD system

P. Lamalle , B. Beaumont , F. Kazarian , T. Gassmann , G. Agarici et al.

Fusion Engineering and Design, 2013, 88 (6-8), pp.517 - 520. ⟨10.1016/j.fusengdes.2012.11.027⟩

Article dans une revue istex cea-04748556v1

CEA contribution to the ITER ICRH antenna design

J.M. Bernard , A. Argouarch , G. Berger-By , C. Brun , F. Clairet et al.

Fusion Engineering and Design, 2013, 88 (6-8), pp.950-955. ⟨10.1016/j.fusengdes.2013.01.040⟩

Article dans une revue istex cea-04738173v1

Developments Toward Fully Metallic Actively Cooled Plasma-Facing Components for the Tungsten Divertor in ITER

X. Courtois , M. Firdaouss , P. Gavila , M. Missirlian , M. Richou et al.

Fusion Science and Technology, 2013, 64 (4), pp.727 - 734. ⟨10.13182/fst13-a24092⟩

Article dans une revue cea-04738476v1
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The WEST project: PFC shaping solutions investigated for the ITER-like W divertor

Marc Missirlian , M. Firdaouss , M. Richou , P. Languille , S. Lecocq et al.

Fusion Engineering and Design, 2013, 88 (9-10), pp.1793-1797. ⟨10.1016/j.fusengdes.2013.03.048⟩

Article dans une revue cea-04724831v1

Science and technology research and development in support to ITER and the Broader Approach at CEA

A. Bécoulet , G.T. Hoang , J. Abiteboul , J. Achard , T. Alarcon et al.

Nuclear Fusion, 2013, 53 (10, SI), ⟨10.1088/0029-5515/53/10/104023⟩

Article dans une revue hal-01287089v1
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Characterization of heat flux generated by ICRH heating with cantilevered bars and a slotted box Faraday screen

Y. Corre , M. Firdaouss , L. Colas , A. Argouarch , D. Guilhem et al.

Nuclear Fusion, 2012, 52 (10), pp.103010. ⟨10.1088/0029-5515/52/10/103010⟩

Article dans une revue cea-04738280v1
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Contribution of Tore Supra in preparation of ITER

B. Saoutic , J. Abiteboul , L. Allegretti , S. Allfrey , J.M. Ané et al.

Nuclear Fusion, 2011, 51 (9), pp.094014. ⟨10.1088/0029-5515/51/9/094014⟩

Article dans une revue istex cea-04738307v2

Heat transfer associated to natural convection flow in a partly porous cavity

Jean-François Mercier , Catherine Weisman , M Firdaouss , Patrick Le Quéré

Journal of Heat Transfer, 2002, 124 (1), pp.130-143. ⟨10.1115/1.1418372⟩

Article dans une revue hal-00990300v1

Some remarks on the acoustic parameters of sharp-edged porous media

M. Firdaouss , J.-L. Guermond , D. Lafarge

International Journal of Engineering Science, 1998, 36 (9), pp.1035-1046. ⟨10.1016/S0020-7225(98)00002-0⟩

Article dans une revue istex hal-02518446v1
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A new design of actively cooled plasma-facing units for the divertors of fusion reactors

J P Gunn , M Firdaouss , M Richou

PSI26 - International Conference on Plasma Surface Interaction, May 2025, Marseille, France. , 2007

Poster de conférence cea-04990021v1
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Thermal loads in gaps between ITER divertor monoblocks: first lessons learnt from WEST

J. P. Gunn , J. Bucalossi , Y. Corre , M. Diez , E. Delmas et al.

PSI 24 - The 24th International Conference on Plasma Surface Interactions in Controlled Fusion, Jan 2021, Jeju, South Korea

Communication dans un congrès cea-03202608v1
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Divertor power loads and scrape off layer width in the large aspect ratio full tungsten tokamak WEST

J. Gaspar , Yann Corre , Clarisse Bourdelle , S. Brezinsek , J. Bucalossi et al.

IAEA FEC 2021 - The 28th IAEA Fusion Energy Conference, May 2021, Nice (Virtual conference), France

Communication dans un congrès cea-03252519v1
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Réduction de modèle thermique par Méthode d'Identification Modale (MIM) pour déterminer la température de surface des composants de machine de fusion

Jonathan Gérardin , Marie-Hélène Aumeunier , Mehdi Firdaouss , Jean-Laurent Gardarein , Fabrice Rigollet

Congrès Français de Thermique 2017, IUSTI & les laboratoires de la fédération Fabri de Peiresc, Aix-Marseille Université, May 2017, Marseille, France. pp.567-574

Communication dans un congrès hal-01795338v1
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Investigation on reduced thermal models for simulating infrared images in fusion devices

J. Gerardin , M-H Aumeunier , M. Firdaouss , J-L Gardarein , Fabrice Rigollet

7th European Thermal-Sciences Conference, Jun 2016, Krakow, Poland. ⟨10.1088/1742-6596/745/3/032019⟩

Communication dans un congrès hal-01794917v1
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Heat Flux estimation in WEST divertor with embedded thermocouples

J. Gaspar , Y. Corre , M. Firdaouss , J.-L. Gardarein , D. Guilhem et al.

7th European Thermal-Sciences Conference, Jun 2016, Krakow, Poland. pp.292 - 303, ⟨10.1088/1742-6596/745/3/032091⟩

Communication dans un congrès hal-01794678v1

Preparing ITER Tungsten Divertor Operation in Tore Supra: Physics Basis for the WEST Project.

E. Tsitrone , C. Bourdelle , J. Bucalossi , R. Guirlet , J.-F. Artaud et al.

25th Fusion Energy Conference (FEC 2014), Oct 2014, Saint Petersburg, Russia. pp.EX/P5-48

Communication dans un congrès hal-02866430v1