Marc Missirlian

Documents

Publications

	A step towards the diagnostic of the ITER first wall: in-situ LIBS measurements in the WEST tokamak Aurélien Favre , Arnaud Bultel , Mamadou Lamine Sankhe , Stéphane Vartanian , Vincent Bruno Physica Scripta, 2024, 99 (3), pp.035609. ⟨10.1088/1402-4896/ad2826⟩ Journal articles hal-04507588v1
	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⟩ Journal articles cea-04590200v1
	Surface heat flux estimation with embedded thermocouples and Fiber Bragg Grating sensor in ITER-like plasma facing components Y. Anquetin , J. Gaspar , Y. Corre , Q. Tichit , J. L. Gardarein Fusion Engineering and Design, 2023, 190, pp.113480. ⟨10.1016/j.fusengdes.2023.113480⟩ Journal articles cea-04087288v1
	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 Nuclear Materials and Energy, 2023, 37, pp.101537. ⟨10.1016/j.nme.2023.101537⟩ Journal articles hal-04396240v1
	Postmortem assessment of the WEST Fiber Bragg grating and thermocouple diagnostic performances with HADES J. Gaspar , Y. Corre , Y. Anquetin , J-L. Gardarein , C. Pocheau Fusion Engineering and Design, 2023, 190, pp.113525. ⟨10.1016/j.fusengdes.2023.113525⟩ Journal articles cea-04087261v1
	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 Fusion Engineering and Design, 2023, 193, pp.113683. ⟨10.1016/j.fusengdes.2023.11368320⟩ Journal articles cea-04619420v1
	Reception tests of the WEST PFUs using ultrasonic testing and infrared thermography M. Ramaniraka , M. Richou , N. Vignal , Y. Addab , M. Missirlian Nuclear Materials and Energy, 2022, 32, pp.101210. ⟨10.1016/j.nme.2022.101210⟩ Journal articles hal-03887799v1
	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 Nuclear Materials and Energy, 2022, 33, pp.101305. ⟨10.1016/j.nme.2022.101305⟩ Journal articles hal-04029665v1
	Thermal loads in gaps between ITER divertor monoblocks: first lessons learnt from WEST J.P. Gunn , J. Bucalossi , Y. Corre , M. Diez , E. Delmas Nuclear Materials and Energy, 2021, 27, pp.100920 Journal articles cea-03202595v1
	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 Fusion Engineering and Design, 2019, 146 part A, pp.757-760. ⟨10.1016/j.fusengdes.2019.01.074⟩ Journal articles hal-02050673v1
	Tungsten coatings repair: An approach to increase the lifetime of plasma facing components M. Diez , M. Firdaouss , M. Richou , Arnaud Bultel , Frédéric Perry Fusion Engineering and Design, 2019, 146, pp.800-804. ⟨10.1016/j.fusengdes.2019.01.084⟩ Journal articles hal-02110735v1
	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 Review of Scientific Instruments, 2018, 89 (6), pp.063508. ⟨10.1063/1.5024514⟩ Journal articles hal-02011117v1
	Measurements and controls implementation for WEST P. Moreau , J. Bucalossi , M. Missirlian , F. Samaille , X. Courtois Fusion Engineering and Design, 2017, 123, pp.1029-1032. ⟨10.1016/j.fusengdes.2017.01.046⟩ Journal articles hal-01785561v1
	Surface heat flux estimation with embedded fiber Bragg gratings measurements: Numerical study J. Gaspar , Y. Corre , J-L. Gardarein , M. Firdaouss , D. Guilhem Nuclear Materials and Energy, 2017, 12, pp.1077 - 1081. ⟨10.1016/j.nme.2016.10.015⟩ Journal articles hal-01794290v1
	Methodology for heat flux investigation on leading edges using infrared thermography Y. Corre , J. -L. Gardarein , R. Dejarnac , J. Gaspar , J. P. Gunn Nuclear Fusion, 2017, 57 (1), ⟨10.1088/0029-5515/57/1/016009⟩ Journal articles hal-01459209v1
	Study of the pores inside tungsten coating after thermal cycling for fusion device C. Desgranges , M. Firdaouss , C. Hernandez , C. Martin , C. Ruset Physica Scripta, 2016, T167, ⟨10.1088/0031-8949/T167/1/014060⟩ Journal articles 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 Fusion Engineering and Design, 2016, 112, pp.1-6. ⟨10.1016/j.fusengdes.2016.07.002⟩ Journal articles hal-01455195v1
	Wall surface temperature calculation in the SolEdge2D-EIRENE transport code Julien Denis , B. Pégourié , J. Bucalossi , Hugo Bufferand , Guido Ciraolo Physica Scripta, 2016, 15th International Conference on Plasma-Facing Materials and Components for Fusion Applications, T167, ⟨10.1088/0031-8949/T167/1/014073⟩ Journal articles hal-01459103v1
	Heat flux distribution and gyro-radius smoothing effect on misaligned CFC tile in the Tore Supra tokamak Yann Corre , Renaud Dejarnac , Jean-Laurent Gardarein , Jonathan Gaspar , Frederic Escourbiac Journal of Nuclear Materials, 2015, 463, pp.832-836. ⟨10.1016/j.jnucmat.2014.10.036⟩ Journal articles hal-01459177v1
	WEST Physics Basis C. Bourdelle , J.F. Artaud , Vincent Basiuk , M. Bécoulet , S. Brémond Nuclear Fusion, 2015, 55 (6), pp.063017. ⟨10.1088/0029-5515/55/6/063017⟩ Journal articles hal-01550957v1
	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 Nuclear Fusion, 2013, 53 (10, SI), ⟨10.1088/0029-5515/53/10/104023⟩ Journal articles hal-01287089v1
	Influence of CFC quality on the performance of TS limiter elements under cyclic heat loading Marc Missirlian , H. Greuner , T. Höschen , Ch. Linsmeier , M. Richou Fusion Engineering and Design, 2011, 86 (9-11), pp.1579-1582. ⟨10.1016/j.fusengdes.2011.03.113⟩ Journal articles hal-04620308v1
	Examination of high heat flux components for the ITER divertor after thermal fatigue testing Marc Missirlian , F. Escourbiac , A. Schmidt , B. Riccardi , I. Bobin-Vastra Journal of Nuclear Materials, 2011, 417 (1-3), pp.597-601. ⟨10.1016/j.jnucmat.2010.12.095⟩ Journal articles hal-04620224v1
	Examination of W7-X target elements after high heat flux testing Marc Missirlian , J. Boscary , A. Durocher , J. Schlosser , H. Greuner Journal of Nuclear Materials, 2009, 386-388, pp.856-859. ⟨10.1016/j.jnucmat.2008.12.269⟩ Journal articles hal-04620255v1
	Damage predictions of carbon fiber composite armoured actively cooled plasma-facing components under cycling heat loads G. Chevet , V. Herb , J. Schlosser , E. Martin , Guy Camus Physica Scripta, 2009, T138 (014057) Journal articles hal-00533365v1
	Investigation of steady-state tokamak issues by long pulse experiments on Tore Supra G. Giruzzi , R. Abgrall , L. Allegretti , J.M. Ané , Paolo Angelino Nuclear Fusion, 2009, 49 (10), pp.104010. ⟨10.1088/0029-5515/49/10/104010⟩ Journal articles hal-03319129v1
	Damage evaluation under thermal fatigue of a vertical target full scale component for the ITER divertor Marc Missirlian , F. Escourbiac , M. Merola , A. Durocher , I. Bobin-Vastra Journal of Nuclear Materials, 2007, 367-370 (Part B), pp.1330-1336. ⟨10.1016/j.jnucmat.2007.03.245⟩ Journal articles hal-04619995v1
	Infrared thermography inspection methods applied to the target elements of W7-X divertor Marc Missirlian , H Traxler , J Boscary , A Durocher , F Escourbiac Fusion Engineering and Design, 2007, 82 (15-24), pp.1747 - 1755. ⟨10.1016/j.fusengdes.2007.05.045⟩ Journal articles hal-04620361v1
	Methodology for the design of diagnostic windows for Tore Supra Marc Missirlian , M Lipa , C Portafaix , C Gil , G Rey Fusion Engineering and Design, 2003, 66-68, pp.911 - 917. ⟨10.1016/s0920-3796(03)00375-2⟩ Journal articles hal-04620424v1
	Design criteria for Tore Supra high heat flux components Marc Missirlian , J Schlosser , M Lipa , R Mitteau , Ph Chappuis Fusion Engineering and Design, 2001, 56-57, pp.457-463. ⟨10.1016/S0920-3796(01)00327-1⟩ Journal articles hal-04620008v1

	Thermal loads in gaps between ITER divertor monoblocks: first lessons learnt from WEST J. P. Gunn , J. Bucalossi , Y. Corre , M. Diez , E. Delmas PSI 24 - The 24th International Conference on Plasma Surface Interactions in Controlled Fusion, Jan 2021, Jeju, South Korea Conference papers cea-03202608v1
	Heat Flux estimation in WEST divertor with embedded thermocouples J. Gaspar , Y. Corre , M. Firdaouss , J.-L. Gardarein , D. Guilhem 7th European Thermal-Sciences Conference, Jun 2016, Krakow, Poland. pp.292 - 303, ⟨10.1088/1742-6596/745/3/032091⟩ Conference papers 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 25th Fusion Energy Conference (FEC 2014), Oct 2014, Saint Petersburg, Russia. pp.EX/P5-48 Conference papers hal-02866430v1

Marc Missirlian

Publications

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

Development of Boron Coatings for antenna protection limiters in the WEST Tokamak

Surface heat flux estimation with embedded thermocouples and Fiber Bragg Grating sensor in ITER-like plasma facing components

Infrared detection of tungsten cracking on actively cooled ITER-like component during high power experiment in WEST

Postmortem assessment of the WEST Fiber Bragg grating and thermocouple diagnostic performances with HADES

Manufacturing, testing and installation of the full tungsten actively cooled ITER-like divertor in the WEST tokamak

Reception tests of the WEST PFUs using ultrasonic testing and infrared thermography

Emissivity measurement of the ITER-like plasma facing components of the WEST phase 2: Pre-exposure measurements and first WEST exposure

Thermal loads in gaps between ITER divertor monoblocks: first lessons learnt from WEST

First heat flux estimation in the lower divertor of WEST with embedded thermal measurements

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

Integration of fiber Bragg grating temperature sensors in plasma facing components of the WEST tokamak

Measurements and controls implementation for WEST

Surface heat flux estimation with embedded fiber Bragg gratings measurements: Numerical study

Methodology for heat flux investigation on leading edges using infrared thermography

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

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

Wall surface temperature calculation in the SolEdge2D-EIRENE transport code

Heat flux distribution and gyro-radius smoothing effect on misaligned CFC tile in the Tore Supra tokamak

WEST Physics Basis

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

Influence of CFC quality on the performance of TS limiter elements under cyclic heat loading

Examination of high heat flux components for the ITER divertor after thermal fatigue testing

Examination of W7-X target elements after high heat flux testing

Damage predictions of carbon fiber composite armoured actively cooled plasma-facing components under cycling heat loads

Investigation of steady-state tokamak issues by long pulse experiments on Tore Supra

Damage evaluation under thermal fatigue of a vertical target full scale component for the ITER divertor

Infrared thermography inspection methods applied to the target elements of W7-X divertor

Methodology for the design of diagnostic windows for Tore Supra

Design criteria for Tore Supra high heat flux components

Thermal loads in gaps between ITER divertor monoblocks: first lessons learnt from WEST

Heat Flux estimation in WEST divertor with embedded thermocouples

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