M. Missirlian - Institute for Research on Fusion by Magnetic confinement, CEA

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A step towards the diagnostic of the ITER first wall: in-situ LIBS measurements in the WEST tokamak

Aurelien Favre,Arnaud Bultel, Mamadou Lamine Sankhe, Stephane Vartanian,Vincent Bruno,Vincent Morel, Daniel L'Hermite,Jean-Baptiste Sirven,Mathilde Diez,Marc Missirlian, Philippe Magaud,Christian Grisolia

PHYSICA SCRIPTAno. 3 (2024)

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HADES - high heat load testing - facility at CEA-IRFM

H. Roche, N. Vignal, A. Bureau,M. Missirlian, A. Martinez, T. Mondière, J-C. Hatchressian, V. Moncada, D. Mouyon, M. Richou

Fusion Engineering and Design (2023): 113769-113769

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Typology of defects in DEMO divertor target mockups

Y. Addab,M. Richou, M. Ramaniraka, N. Vignal, E. Visca,G. Dose,S. Roccella, H. Greuner,M. Missirlian,J. H. You

PHYSICA SCRIPTA（2021）

引用2浏览0引用

Design And Integration Of Femtosecond Fiber Bragg Gratings Temperature Probes Inside Actively Cooled Iter-Like Plasma-Facing Components

N. Chanet,Y. Corre, R. Cotillard,J. Gaspar, G. Laffont, C. Pocheau,G. Caulier, C. Dechelle, B. De Gentile,C. Destouches, L. Dubus, F. Gallay,

FUSION ENGINEERING AND DESIGN（2021）

引用8浏览0引用

Acceptance Tests Of The Industrial Series Manufacturing Of West Iter-Like Tungsten Actively Cooled Divertor

Marianne Richou,Marc Missirlian,Mehdi Firdaouss, Bernd Boeswirth,Mathilde Diez,Henri Greuner,Jean-Claude Hatchressian, Nadia Perot, Manda Ramaniraka,Helene Roche

PHYSICA SCRIPTA（2021）

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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,N. Fedorczak,A. Grosjean, M. Firdaouss,J. Gaspar,T. Loarer,M. Missirlian,P. Moreau,

Nuclear Materials and Energy（2021）

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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, R. Cotillard,J. Gaspar, G. Laffont, C. Pocheau,G. Caulier,C. Destouches,J-L. Gardarein, M. Firdaouss, M. Houry,M. Missirlian,

FUSION ENGINEERING AND DESIGN（2021）

引用6浏览0引用

Performance assessment of thick W/Cu graded interlayer for DEMO divertor target

M. Richou, F. Gallay,B. Böswirth, I. Chu,G. Dose,H. Greuner,G. Kermouche,M. Lenci,Th. Loewenhoff, R. Maestracci, E. Meillot,M. Missirlian,

Fusion Engineering and Design（2020）

引用26浏览0引用

Impact of Misalignments on ITER-like Plasma Facing Components in WEST Tokamak

A. Grosjean,Yann Corre,R. Dejarnac,J. Gaspar,J. P. Gunn, E. Bernard, S. Carpentier-Chouchana,X. Courtois,E. Delmas,M. Diez, L. Dubus, A. Durocher,

symposium on fusion technology (2020)

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Tungsten coatings repair: An approach to increase the lifetime of plasma facing components

M. Diez,M. Firdaouss,M. Richou,A. Bultel, F. Perry,H. Roche,C. Grisolia,M. Missirlian

FUSION ENGINEERING AND DESIGN（2019）

引用8浏览0引用

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