Marc Missirlian Ingénieur-Chercheur CEA

Identifiants chercheurs

IdHAL :

marc-missirlian

ORCID :

0000-0003-2213-9225

Présentation

Ingénieur-Chercheur CEA

Publications

Article dans une revue (95)

WEST full tungsten operation with an ITER grade divertor J. Bucalossi,A. Ekedahl,J. Achard,K. Afonin,O. Agulloet al. Nuclear Fusion, 2024, 64 (11), pp.112022. ⟨10.1088/1741-4326/ad64e5⟩ Article dans une revue hal-04948518v1
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
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 Brunoet al. Physica Scripta, 2024, 99 (3), pp.035609. ⟨10.1088/1402-4896/ad2826⟩ Article dans une revue hal-04507588v1
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. Missirlianet al. Fusion Engineering and Design, 2024, 199, pp.114133. ⟨10.1016/j.fusengdes.2023.114133⟩ Article dans une revue cea-04748693v1
HADES - high heat load testing - facility at CEA-IRFM H. Roche,N. Vignal,A. Bureau,M. Missirlian,A. Martinezet al. Fusion Engineering and Design, 2023, 192, pp.113769. ⟨10.1016/j.fusengdes.2023.113769⟩ Article dans une revue cea-04746520v1
Postmortem assessment of the WEST Fiber Bragg grating and thermocouple diagnostic performances with HADES J. Gaspar,Y. Corre,Y. Anquetin,J-L. Gardarein,C. Pocheauet al. Fusion Engineering and Design, 2023, 190, pp.113525. ⟨10.1016/j.fusengdes.2023.113525⟩ Article dans une revue 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 Gargiuloet al. Fusion Engineering and Design, 2023, 193, pp.113683. ⟨10.1016/j.fusengdes.2023.113683⟩ Article dans une revue cea-04619420v1
Surface heat flux estimation with embedded thermocouples and Fiber Bragg Grating sensor in ITER-like plasma facing components Yann Anquetin,J. Gaspar,Yann Corre,Quentin Tichit,Jean-Laurent Gardareinet al. Fusion Engineering and Design, 2023, 190, pp.113480. ⟨10.1016/j.fusengdes.2023.113480⟩ Article dans une revue 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. Correet al. Nuclear Materials and Energy, 2023, 37, pp.101537. ⟨10.1016/j.nme.2023.101537⟩ Article dans une revue hal-04396240v1
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⟩ Article dans une revue 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. Bernardet al. Nuclear Materials and Energy, 2022, 33, pp.101305. ⟨10.1016/j.nme.2022.101305⟩ Article dans une revue hal-04029665v1
Acceptance tests of the industrial series manufacturing of WEST ITER-like tungsten actively cooled divertor Marianne Richou,Marc Missirlian,Mehdi Firdaouss,Bernd Böswirth,Mathilde Diezet al. Physica Scripta, 2021, 96 (12), pp.124029. ⟨10.1088/1402-4896/ac2657⟩ Article dans une revue hal-04768143v1
Thermal loads in gaps between ITER divertor monoblocks: first lessons learnt from WEST J.P. Gunn,J. Bucalossi,Y. Corre,M. Diez,E. Delmaset al. Nuclear Materials and Energy, 2021, 27, pp.100920. ⟨10.1016/j.nme.2021.100920⟩ Article dans une revue cea-03202595v1
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. Firdaousset al. Nuclear Fusion, 2021, 61 (10), pp.106011. ⟨10.1088/1741-4326/ac1dc6⟩ Article dans une revue cea-04746758v1
High heat flux testing of newly developed tungsten components for WEST G. Pintsuk,M. Missirlian,G.-N. Luo,Q. Li,W. Wanget al. Fusion Engineering and Design, 2021, 173, pp.112835. ⟨10.1016/j.fusengdes.2021.112835⟩ Article dans une revue cea-04746703v1
Sustained W-melting experiments on actively cooled ITER-like Plasma Facing Unit in WEST Yann Corre,Alex Grosjean,James P. Gunn,Karl Krieger,Svetlana Ratynskaiaet al. Physica Scripta, 2021, 96 (12), pp.124057. ⟨10.1088/1402-4896/ac326a⟩ Article dans une revue hal-03583706v1
Performance assessment of thick W/Cu graded interlayer for DEMO divertor target M. Richou,F. Gallay,B. Böswirth,I. Chu,G. Doseet al. Fusion Engineering and Design, 2020, 157, pp.111610. ⟨10.1016/j.fusengdes.2020.111610⟩ Article dans une revue cea-04747927v1
First heat flux estimation in the lower divertor of WEST with embedded thermal measurements J. Gaspar,Y. Corre,M. Firdaouss,J.L. Gardarein,J. Gerardinet 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
Thermomechanical simulation of flat tiles mock-ups under high heat flux T. Batal,M. Missirlian,A. Durif,G.N. Luo,Q. Liet al. Fusion Engineering and Design, 2019, 146, pp.2153-2157. ⟨10.1016/j.fusengdes.2019.03.127⟩ Article dans une revue cea-04748746v1
Tungsten coatings repair: An approach to increase the lifetime of plasma facing components Mathilde Diez,Mehdi Firdaouss,Marianne Richou,Arnaud Bultel,Frédéric Perryet al. Fusion Engineering and Design, 2019, 146, pp.800-804. ⟨10.1016/j.fusengdes.2019.01.084⟩ Article dans une revue hal-02110735v1
Qualification and post-mortem investigation of actively cooled tungsten flat-tile mock-ups for WEST divertor Marc Missirlian,G. Pintsuk,G.-N. Luo,Q. Li,W. Wanget al. Fusion Engineering and Design, 2018, 136, pp.403-409. ⟨10.1016/j.fusengdes.2018.02.063⟩ Article dans une revue cea-04724777v1
Effect of induction heating on flaw generation and expansion M. Richou,F. Gallay,N. Vignal,M. Missirlian Fusion Engineering and Design, 2018, 136, pp.1273-1277. ⟨10.1016/j.fusengdes.2018.04.116⟩ Article dans une revue cea-04746353v1
Integration of fiber Bragg grating temperature sensors in plasma facing components of the WEST tokamak Yann Corre,Guillaume Laffont,Christine Pocheau,Romain Cotillard,Jonathan Gasparet al. Review of Scientific Instruments, 2018, 89 (6), pp.063508. ⟨10.1063/1.5024514⟩ Article dans une revue hal-02011117v1
Status on the W monoblock type high heat flux target with graded interlayer for application to DEMO divertor M. Richou,F. Gallay,P. Magaud,M. Missirlian,S. Rocellaet al. Fusion Engineering and Design, 2017, 124, pp.338 - 343. ⟨10.1016/j.fusengdes.2017.03.087⟩ Article dans une revue cea-04748567v1
Potential approach of IR-analysis for high heat flux quality assessment of divertor tungsten monoblock components Henri Greuner,B. Böswirth,H. Maier,T. Hirai,S. Panayotiset al. Fusion Engineering and Design, 2017, 124, pp.202 - 206. ⟨10.1016/j.fusengdes.2017.02.092⟩ Article dans une revue cea-04748493v1
Surface heat loads on the ITER divertor vertical targets J.P. Gunn,S. Carpentier-Chouchana,F. Escourbiac,T. Hirai,S. Panayotiset al. Nuclear Fusion, 2017, 57 (4), pp.046025. ⟨10.1088/1741-4326/aa5e2a⟩ Article dans une revue cea-04748589v1
Results of high heat flux qualification tests of W monoblock components for WEST H Greuner,B Böswirth,M Lipa,M. Missirlian,M. Richou Physica Scripta, 2017, T170, pp.014001. ⟨10.1088/0031-8949/2017/t170/014001⟩ Article dans une revue cea-04748523v1
Methodology for heat flux investigation on leading edges using infrared thermography Y. Corre,J. -L. Gardarein,R. Dejarnac,J. Gaspar,J. P. Gunnet al. Nuclear Fusion, 2017, 57 (1), ⟨10.1088/0029-5515/57/1/016009⟩ Article dans une revue hal-01459209v1
Overview of the different processes of tungsten coating implemented into WEST tokamak M. Firdaouss,C. Desgranges,C. Hernandez,M. Richou,H. Greuneret 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 decade-long development of plasma-facing components at ASIPP G.-N. Luo,G.H. Liu,Q. Li,S.G. Qin,W.J. Wanget al. Nuclear Fusion, 2017, 57 (6), pp.065001. ⟨10.1088/1741-4326/aa6502⟩ Article dans une revue cea-04747904v1
Measurements and controls implementation for WEST P. Moreau,J. Bucalossi,M. Missirlian,F. Samaille,X. Courtoiset al. Fusion Engineering and Design, 2017, 123, pp.1029-1032. ⟨10.1016/j.fusengdes.2017.01.046⟩ Article dans une revue hal-01785561v1
Surface heat flux estimation with embedded fiber Bragg gratings measurements: Numerical study J. Gaspar,Y. Corre,J-L. Gardarein,M. Firdaouss,D. Guilhemet al. Nuclear Materials and Energy, 2017, 12, pp.1077 - 1081. ⟨10.1016/j.nme.2016.10.015⟩ Article dans une revue hal-01794290v1
Mechanical analysis of WEST divertor support plate T. Batal,F. Ferlay,S. Burles,S. Larroque,L. Doceulet al. Fusion Engineering and Design, 2017, 124, pp.302-305. ⟨10.1016/j.fusengdes.2017.04.006⟩ Article dans une revue cea-04747858v1
Study of the pores inside tungsten coating after thermal cycling for fusion device C. Desgranges,M. Firdaouss,C. Hernandez,C. Martin,C. Rusetet 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. Bucalossiet al. Fusion Engineering and Design, 2016, 112, pp.1-6. ⟨10.1016/j.fusengdes.2016.07.002⟩ Article dans une revue istex hal-01455195v1
Wall surface temperature calculation in the SolEdge2D-EIRENE transport code Julien Denis,B. Pégourié,J. Bucalossi,Hugo Bufferand,Guido Ciraoloet al. Physica Scripta, 2016, 15th International Conference on Plasma-Facing Materials and Components for Fusion Applications, T167, ⟨10.1088/0031-8949/T167/1/014073⟩ Article dans une revue hal-01459103v1
Thermomechanical simulation of WEST actively cooled upper divertor T. Batal,M. Richou,D. Guilhem,M. Firdaouss,S. Larroqueet 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 Ferlayet al. Physica Scripta, 2016, T167, pp.014066. ⟨10.1088/0031-8949/t167/1/014066⟩ Article dans une revue cea-04748773v1
A fatigue lifetime assessment of WEST ITER Like Plasma Facing Unit P. Languille,Marc Missirlian,D. Guilhem,F. Ferlay,T. Batalet al. Fusion Engineering and Design, 2016, 109-111, pp.294-298. ⟨10.1016/j.fusengdes.2016.03.009⟩ Article dans une revue cea-04723407v1
WEST Physics Basis C. Bourdelle,J.F. Artaud,Vincent Basiuk,M. Bécoulet,S. Brémondet 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. Languilleet 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
Plasma facing components integration studies for the WEST divertor Fabien Ferlay,Marc Missirlian,Dominique Guilhem,Mehdi Firdaouss,Marianne Richouet 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 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 Escourbiacet al. Journal of Nuclear Materials, 2015, 463, pp.832-836. ⟨10.1016/j.jnucmat.2014.10.036⟩ Article dans une revue istex hal-01459177v1
The WEST project: Current status of the ITER-like tungsten divertor Marc Missirlian,J. Bucalossi,Y. Corre,F. Ferlay,M. Firdaousset 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
Implementation of a design and configuration management platform for fusion components on the Tore Supra WEST Project Fabrice Benoît,Ludovic Allegretti,Marie-Hélène Aumeunier,Jérôme Bucalossi,Louis Doceulet al. Fusion Engineering and Design, 2014, 89 (9-10), pp.1928 - 1932. ⟨10.1016/j.fusengdes.2014.03.047⟩ Article dans une revue cea-04746730v1
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. Tsitroneet 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
The WEST Project: Challenges of Diagnostic Integration Sophie Salasca,Jerome Bucalossi,Emmanuelle Tsitrone,Christel Fenzi,Frank Samailleet al. IEEE Transactions on Plasma Science, 2014, 42 (5), pp.1449-1456. ⟨10.1109/TPS.2014.2314648⟩ Article dans une revue cea-04748636v1
Improvement of non destructive infrared test bed SATIR for examination of actively cooled tungsten armour Plasma Facing Components N. Vignal,C. Desgranges,V. Cantone,M. Richou,X. Courtoiset al. Fusion Engineering and Design, 2013, 88 (9-10), pp.1818 - 1822. ⟨10.1016/j.fusengdes.2013.05.053⟩ Article dans une revue cea-04746748v1
Upgrades of the tore Supra water cooling system for the WEST project A. Martinez,J. Bucalossi,M. Chantant,M. Missirlian,C. Portafaixet al. Fusion Engineering and Design, 2013, 88 (6-8), pp.804 - 808. ⟨10.1016/j.fusengdes.2013.03.042⟩ Article dans une revue istex cea-04748788v1
Status of the ITER Ion Cyclotron H&CD system P. Lamalle,B. Beaumont,F. Kazarian,T. Gassmann,G. Agariciet 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. Clairetet 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. Richouet al. Fusion Science and Technology, 2013, 64 (4), pp.727 - 734. ⟨10.13182/fst13-a24092⟩ Article dans une revue cea-04738476v1
Design optimization of plasma facing component with functional gradient material Cu/W interlayer E. Autissier,M. Richou,F. Bernard,M. Missirlian Fusion Engineering and Design, 2013, 88 (9-10), pp.1714 - 1717. ⟨10.1016/j.fusengdes.2013.04.042⟩ Article dans une revue istex cea-04738422v1
Potential and limits of water cooled divertor concepts based on monoblock design as possible candidates for a DEMO reactor Antonella Li-Puma,Marianne Richou,Philippe Magaud,Marc Missirlian,Eliseo Viscaet al. Fusion Engineering and Design, 2013, 88 (9-10), pp.1836-1843. ⟨10.1016/j.fusengdes.2013.05.114⟩ Article dans une revue istex cea-04748480v1
The WEST programme: Minimizing technology and operational risks of a full actively cooled tungsten divertor on ITER André Grosman,Jérôme Bucalossi,Louis Doceul,Frédéric Escourbiac,Manfred Lipaet al. Fusion Engineering and Design, 2013, 88 (6-8), pp.497-500. ⟨10.1016/j.fusengdes.2013.02.039⟩ Article dans une revue istex cea-04748617v1
Plasma facing components: challenges for nuclear materials Philippe Magaud,Jérôme Bucalossi,Antonella Li Puma,Marc Missirlian,Marianne Richou EPJ Web of Conferences, 2013, 51, pp.04005. ⟨10.1051/epjconf/20135104005⟩ Article dans une revue cea-04748467v1
The WEST project: PFC shaping solutions investigated for the ITER-like W divertor Marc Missirlian,M. Firdaouss,M. Richou,P. Languille,S. Lecocqet 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. Alarconet al. Nuclear Fusion, 2013, 53 (10, SI), ⟨10.1088/0029-5515/53/10/104023⟩ Article dans une revue hal-01287089v1
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. Guilhemet al. Nuclear Fusion, 2012, 52 (10), pp.103010. ⟨10.1088/0029-5515/52/10/103010⟩ Article dans une revue cea-04738280v1
High heat flux testing of mock-ups for a full tungsten ITER divertor P. Gavila,B. Riccardi,S. Constans,J.L. Jouvelot,I. Bobin Vastraet al. Fusion Engineering and Design, 2011, 86 (9-11), pp.1652-1655. ⟨10.1016/j.fusengdes.2011.02.012⟩ Article dans une revue istex cea-04746682v1
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⟩ Article dans une revue istex hal-04620224v1
Contribution of Tore Supra in preparation of ITER B. Saoutic,J. Abiteboul,L. Allegretti,S. Allfrey,J.M. Anéet al. Nuclear Fusion, 2011, 51 (9), pp.094014. ⟨10.1088/0029-5515/51/9/094014⟩ Article dans une revue istex cea-04738307v2
Influence of CFC quality on the performance of TS limiter elements under cyclic heat loading Marc Missirlian,H. Greuner,T. Höschen,Ch. Linsmeier,M. Richouet al. Fusion Engineering and Design, 2011, 86 (9-11), pp.1579-1582. ⟨10.1016/j.fusengdes.2011.03.113⟩ Article dans une revue istex hal-04620308v1
Engineering studies for the installation of an axi-symmetric metallic divertor in Tore Supra L. Doceul,C. Portafaix,J. Bucalossi,A. Saille,B. Bertrandet al. Fusion Engineering and Design, 2011, 86 (9-11), pp.1660 - 1664. ⟨10.1016/j.fusengdes.2011.02.063⟩ Article dans une revue cea-04746374v1
Feasibility study of an actively cooled tungsten divertor in Tore Supra for ITER technology testing J. Bucalossi,A. Argouarch,V. Basiuk,O. Baulaigue,P. Bayettiet al. Fusion Engineering and Design, 2011, 86 (6-8), pp.684 - 688. ⟨10.1016/j.fusengdes.2011.01.114⟩ Article dans une revue cea-04746467v1
Manufacturing process and tests of a lower hybrid passive active multi-junction launcher for long pulse experiments on Tore-Supra D. Guilhem,B. Bertrand,M. Lipa,J. Achard,G. Agariciet al. Fusion Engineering and Design, 2011, 86 (4-5), pp.279 - 287. ⟨10.1016/j.fusengdes.2011.01.057⟩ Article dans une revue cea-04746912v1
The heat removal capability of actively cooled plasma-facing components for the ITER divertor Marc Missirlian,M Richou,B Riccardi,P Gavila,T Loareret al. Physica Scripta, 2011, 2011 (T145), pp.014080. ⟨10.1088/0031-8949/2011/T145/014080⟩ Article dans une revue cea-04724810v1
Evolution of the bonding defect reported on the tiles of the toroidal pumped limiter of the Tore Supra tokamak with infrared analysis Laizhong Cai,Eric Gauthier,Yann Corre,Thierry Loarer,Marc Missirlianet al. Physica Scripta, 2011, 85 (1), pp.015501. ⟨10.1088/0031-8949/85/01/015501⟩ Article dans une revue cea-04746429v1
Characterization and damaging law of CFC for high heat flux actively cooled plasma facing components G. Chevet,E. Martin,J. Boscary,G. Camus,V. Herbet al. Journal of Nuclear Materials, 2011, 417 (1-3), pp.643-646. ⟨10.1016/j.jnucmat.2011.01.073⟩ Article dans une revue istex cea-04738235v1
Micro-chemical analysis of high heat loaded CFC–Cu interfaces from Tore Supra and Wendelstein 7-X Ch Linsmeier,H Greuner,M. Missirlian,T. Hoschen Physica Scripta, 2011, T145 (1), pp.014079. ⟨10.1088/0031-8949/2011/t145/014079⟩ Article dans une revue cea-04747878v1
Fatigue lifetime of repaired high heat flux components for ITER divertor M. Richou,M. Missirlian,B. Riccardi,P. Gavila,C. Desgrangeset al. Fusion Engineering and Design, 2011, 86 (9-11), pp.1771-1775. ⟨10.1016/j.fusengdes.2011.03.020⟩ Article dans une revue istex cea-04746452v1
Manufacturing process and tests of a Lower Hybrid Passive–Active Multijunction launcher for long pulse experiments on Tore-Supra D. Guilhem,F. Samaille,B. Bertrand,M. Lipa,J. Achardet al. Fusion Engineering and Design, 2011, 86 (6-8), pp.513-517. ⟨10.1016/j.fusengdes.2011.02.006⟩ Article dans une revue istex cea-04747486v1
Recent development toward the use of infrared thermography as a non destructive technique for defect detection in tungsten plasma facing components M. Richou,F. Escourbiac,M. Missirlian,N. Vignal,V. Cantoneet al. Journal of Nuclear Materials, 2011, Proceedings of ICFRM-14, 417 (1-3), pp.581 - 585. ⟨10.1016/j.jnucmat.2010.12.255⟩ Article dans une revue istex cea-04748505v1
Damage predictions of carbon fiber composite armoured actively cooled plasma-facing components under cycling heat loads G. Chevet,V. Herb,J. Schlosser,Eric Martin,Guy Camuset al. Physica Scripta, 2009, T138 (014057), ⟨10.1088/0031-8949/2009/T138/014057⟩ Article dans une revue istex hal-00533365v1
Passive Active Multi-Junction 3, 7 GHZ launcher for Tore-Supra Long Pulse Experiments. Manufacturing Process and Tests D. Guilhem,J. Achard,J. Belo,B. Bertrand,Z. Bejet al. AIP Conference Proceedings, 2009, pp.435-438. ⟨10.1063/1.3273786⟩ Article dans une revue cea-04747920v1
Upgraded acceptance criteria from transient thermography control for the W7-X divertor target elements Marc Missirlian,J. Boscary,R. Guigon,J. Schlosser,A. Durocheret al. Fusion Engineering and Design, 2009, 84 (7-11), pp.1317-1322. ⟨10.1016/j.fusengdes.2008.12.080⟩ Article dans une revue istex cea-04724837v1
Diagnostic systems on Tore Supra C. Gil,C. de Michelis,D. Elbeze,C. Fenzi,J P Gunnet al. Fusion Science and Technology, 2009, 56 (3), pp.1219 - 1252. ⟨10.13182/fst09-a9175⟩ Article dans une revue cea-04746344v1
Innovative image processing techniques applied to the thermographic inspection of PFC with SATIR facility R. Guigon,C. Le Niliot,M. Missirlian,X. Courtois,F. Cismondi Fusion Engineering and Design, 2009, 84 (2-6), pp.859 - 863. ⟨10.1016/j.fusengdes.2008.11.034⟩ Article dans une revue cea-04746876v1
Examination of W7-X target elements after high heat flux testing Marc Missirlian,J. Boscary,A. Durocher,J. Schlosser,H. Greuneret al. Journal of Nuclear Materials, 2009, 386-388, pp.856-859. ⟨10.1016/j.jnucmat.2008.12.269⟩ Article dans une revue istex hal-04620255v1
Advanced qualification methodology for actively cooled plasma facing components Alain Durocher,Frederic Escourbiac,Andre Grosman,J. Boscary,Mario Merolaet al. Nuclear Fusion, 2008, 48 (7), pp.079801. ⟨10.1088/0029-5515/48/7/079801⟩ Article dans une revue cea-04731109v1
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-Vastraet al. Journal of Nuclear Materials, 2007, 367-370 (Part B), pp.1330-1336. ⟨10.1016/j.jnucmat.2007.03.245⟩ Article dans une revue istex hal-04619995v1
Qualification of high heat flux components: application to target elements of W7-X divertor Marc Missirlian,A Durocher,A Grosman,J Schlosser,J Boscaryet al. Physica Scripta, 2007, 2007 (T128), pp.182-188. ⟨10.1088/0031-8949/2007/T128/035⟩ Article dans une revue cea-04724800v1
Infrared thermography inspection methods applied to the target elements of W7-X divertor Marc Missirlian,H Traxler,J Boscary,A Durocher,F Escourbiacet al. Fusion Engineering and Design, 2007, 82 (15-24), pp.1747 - 1755. ⟨10.1016/j.fusengdes.2007.05.045⟩ Article dans une revue hal-04620361v1
Infrared images data merging for plasma-facing component inspection A. Durocher,J. Moysan,F. Escourbiac,M. Missirlian,N. Vignalet al. Fusion Engineering and Design, 2007, 82 (15-24), pp.1694-1699. ⟨10.1016/j.fusengdes.2007.07.040⟩ Article dans une revue cea-04746845v1
Acceptance criteria for the ITER divertor vertical target S. Fouquet,J. Schlosser,M. Merola,A. Durocher,F. Escourbiacet al. Fusion Engineering and Design, 2006, 81 (1-7), pp.265 - 268. ⟨10.1016/j.fusengdes.2005.06.363⟩ Article dans une revue cea-04731019v1
Results and analysis of high heat flux tests on a full-scale vertical target prototype of ITER divertor Marc Missirlian,F. Escourbiac,M. Merola,I. Bobin-Vastra,J. Schlosseret al. Fusion Engineering and Design, 2005, 75-79, pp.435-440. ⟨10.1016/j.fusengdes.2005.06.168⟩ Article dans une revue istex cea-04724803v1
Tore-Supra infrared thermography system, a real steady-state diagnostic D. Guilhem,J.L. Bondil,B. Bertrand,C. Desgranges,M. Lipaet al. Fusion Engineering and Design, 2005, Part of special issue Proceedings of the 23rd Symposium of Fusion Technology: SOFT 23 Edited by F. Gnesotto, R. Piovan, M. Basso, 74 (1-4), pp.879 - 883. ⟨10.1016/j.fusengdes.2005.08.021⟩ Article dans une revue istex cea-04748768v1
Infrared surface temperature measurements for long pulse operation, and real time feedback control in Tore-Supra, an actively cooled Tokamak D. Guilhem,B. Adjeroud,C. Balorin,Y. Buravand,B. Bertrandet al. Quantitative InfraRed Thermography Journal, 2005, 2 (1), pp.77-96. ⟨10.3166/qirt.2.77-96⟩ Article dans une revue cea-04730709v1
A mature industrial solution for ITER divertor plasma facing components: Hypervapotron cooling concept adapted to Tore Supra flat tile technology F. Escourbiac,I. Bobin-Vastra,V. Kuznetsov,M. Missirlian,B. Schedleret al. Fusion Engineering and Design, 2005, 75-79, pp.387 - 390. ⟨10.1016/j.fusengdes.2005.06.328⟩ Article dans une revue cea-04730903v1
Hot spot effect on infrared spectral luminance emitted by carbon under plasma particles impact E. Delchambre,R. Reichle,R. Mitteau,M. Missirlian,P. Roubin Journal of Nuclear Materials, 2005, 337-339, pp.1069 - 1072. ⟨10.1016/j.jnucmat.2004.10.015⟩ Article dans une revue cea-04746717v1
ITER-like PAM launcher for Tore Supra's LHCD system J.H. Belo,Ph H Bibet,M. Missirlian,J. Achard,B. Beaumontet al. Fusion Engineering and Design, 2005, 74 (1-4), pp.283 - 288. ⟨10.1016/j.fusengdes.2005.06.173⟩ Article dans une revue cea-04746903v1
Thermal behaviour of redeposited layer under high heat flux exposure E. Gauthier,S. Dumas,J. Matheus,M. Missirlian,Y. Correet al. Journal of Nuclear Materials, 2005, 337-339, pp.960 - 964. ⟨10.1016/j.jnucmat.2004.10.161⟩ Article dans une revue cea-04748699v1
Flat Tile Armour Cooled by Hypervapotron Tube: a Possible Technology for ITER J. Schlosser,F. Escourbiac,M. Merola,B. Schedler,P. Bayettiet al. Physica Scripta, 2004, T111 (1), pp.199. ⟨10.1238/Physica.Topical.111a00199⟩ Article dans une revue cea-04746504v1
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⟩ Article dans une revue hal-04620424v1
Design criteria for Tore Supra high heat flux components Marc Missirlian,J Schlosser,M Lipa,R Mitteau,Ph Chappuiset al. Fusion Engineering and Design, 2001, 56-57, pp.457-463. ⟨10.1016/S0920-3796(01)00327-1⟩ Article dans une revue istex hal-04620008v1

Communication dans un congrès (5)

Thermal loads in gaps between ITER divertor monoblocks: first lessons learnt from WEST J. P. Gunn,J. Bucalossi,Y. Corre,M. Diez,E. Delmaset 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
Heat Flux estimation in WEST divertor with embedded thermocouples J. Gaspar,Y. Corre,M. Firdaouss,J.-L. Gardarein,D. Guilhemet 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. Artaudet al. 25th Fusion Energy Conference (FEC 2014), Oct 2014, Saint Petersburg, Russia. pp.EX/P5-48 Communication dans un congrès hal-02866430v1
Diagnostic integration issues in the Tore Supra upgrade project WEST S. Salasca,J. Bucalossi,E. Tsitrone,C. Fenzi,F. Samailleet al. 2013 IEEE 25th Symposium on Fusion Engineering (SOFE), Jun 2013, San Francisco (CA), United States. pp.1-6, ⟨10.1109/SOFE.2013.6635409⟩ Communication dans un congrès cea-04738544v1
ITER like lower hybrid passive active multi-junction antenna manufacturing D. Guilhem,F. Samaille,B. Bertrand,M. Lipa,J. Achardet al. 2011 IEEE/NPSS 24th Symposium on Fusion Engineering, Jun 2011, Chicago, United States. ⟨10.1109/SOFE.2011.6052318⟩ Communication dans un congrès cea-04746892v1

Poster de conférence (1)

LIBS (laser-induced breakdown spectroscopy) applications for the tritium measurement in tokamak plasma-facing components Arnaud Bultel,Aurélien Favre,Vincent Morel,Floriane Leblond,Mickael Payetet al. ICPIG 2025 - International Conférence on Phenomena in Ionized Gases, Jul 2025, Aix-en-Provence, France Poster de conférence hal-05194223v1

N°spécial de revue/special issue (1)

Calculation of heat fluxes induced by radio frequency heating on the actively cooled protections of ion cyclotron resonant heating (ICRH) and lower hybrid (LH) antennas in Tore Supra G. Ritz,Y. Corre,M. Rault,M. Missirlian,C. Portafaixet al. Fusion Engineering and Design, 88 (6-8), pp.899 - 902, 2013, Part of special issue Proceedings of the 27th Symposium On Fusion Technology (SOFT-27); Liège, Belgium, September 24-28, 2012, ⟨10.1016/j.fusengdes.2013.01.045⟩ N°spécial de revue/special issue istex cea-04731134v1