Marc Missirlian

Ingénieur-Chercheur CEA
64%
Libre accès
100
Documents
Affiliations actuelles
  • Institut de Recherche sur la Fusion par confinement Magnétique (IRFM)
  • CEA Cadarache
Identifiants chercheurs

Présentation

Ingénieur-Chercheur CEA

Domaines de recherche

Physique [physics] Sciences de l'ingénieur [physics]

Publications

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Publications

Image document

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-04948518 v1
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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-04590200 v1

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 et al.
Physica Scripta, 2024, 99 (3), pp.035609. ⟨10.1088/1402-4896/ad2826⟩
Article dans une revue hal-04507588 v1
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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-04748693 v1
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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-04619420 v1
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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 et al.
Fusion Engineering and Design, 2023, 190, pp.113525. ⟨10.1016/j.fusengdes.2023.113525⟩
Article dans une revue cea-04087261 v1
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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 et al.
Fusion Engineering and Design, 2023, 190, pp.113480. ⟨10.1016/j.fusengdes.2023.113480⟩
Article dans une revue cea-04087288 v1
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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-04396240 v1

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

H. Roche , N. Vignal , A. Bureau , M. Missirlian , A. Martinez et al.
Fusion Engineering and Design, 2023, 192, pp.113769. ⟨10.1016/j.fusengdes.2023.113769⟩
Article dans une revue cea-04746520 v1
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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-03887799 v1
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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-04029665 v1
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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-03202595 v1

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-04768143 v1
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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-04746758 v1
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High heat flux testing of newly developed tungsten components for WEST

G. Pintsuk , M. Missirlian , G.-N. Luo , Q. Li , W. Wang et al.
Fusion Engineering and Design, 2021, 173, pp.112835. ⟨10.1016/j.fusengdes.2021.112835⟩
Article dans une revue cea-04746703 v1

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

M. Richou , F. Gallay , B. Böswirth , I. Chu , G. Dose et al.
Fusion Engineering and Design, 2020, 157, pp.111610. ⟨10.1016/j.fusengdes.2020.111610⟩
Article dans une revue cea-04747927 v1
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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-02050673 v1

Thermomechanical simulation of flat tiles mock-ups under high heat flux

T. Batal , M. Missirlian , A. Durif , G.N. Luo , Q. Li et al.
Fusion Engineering and Design, 2019, 146, pp.2153-2157. ⟨10.1016/j.fusengdes.2019.03.127⟩
Article dans une revue cea-04748746 v1
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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-02110735 v1
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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. Wang et al.
Fusion Engineering and Design, 2018, 136, pp.403-409. ⟨10.1016/j.fusengdes.2018.02.063⟩
Article dans une revue cea-04724777 v1

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-04746353 v1
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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-02011117 v1
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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. Panayotis et al.
Fusion Engineering and Design, 2017, 124, pp.202 - 206. ⟨10.1016/j.fusengdes.2017.02.092⟩
Article dans une revue cea-04748493 v1

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. Rocella et al.
Fusion Engineering and Design, 2017, 124, pp.338 - 343. ⟨10.1016/j.fusengdes.2017.03.087⟩
Article dans une revue cea-04748567 v1

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-04748523 v1
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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-04748589 v1

Methodology for heat flux investigation on leading edges using infrared thermography

Y. Corre , J. -L. Gardarein , R. Dejarnac , J. Gaspar , J. P. Gunn et al.
Nuclear Fusion, 2017, 57 (1), ⟨10.1088/0029-5515/57/1/016009⟩
Article dans une revue hal-01459209 v1

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-04747908 v1
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Overview of decade-long development of plasma-facing components at ASIPP

G.-N. Luo , G.H. Liu , Q. Li , S.G. Qin , W.J. Wang et al.
Nuclear Fusion, 2017, 57 (6), pp.065001. ⟨10.1088/1741-4326/aa6502⟩
Article dans une revue cea-04747904 v1

Measurements and controls implementation for WEST

P. Moreau , J. Bucalossi , M. Missirlian , F. Samaille , X. Courtois et al.
Fusion Engineering and Design, 2017, 123, pp.1029-1032. ⟨10.1016/j.fusengdes.2017.01.046⟩
Article dans une revue hal-01785561 v1
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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-01794290 v1

Mechanical analysis of WEST divertor support plate

T. Batal , F. Ferlay , S. Burles , S. Larroque , L. Doceul et al.
Fusion Engineering and Design, 2017, 124, pp.302-305. ⟨10.1016/j.fusengdes.2017.04.006⟩
Article dans une revue cea-04747858 v1

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 hal-01455195 v1

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-01455190 v1

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 cea-04748752 v1

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-04748773 v1
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Wall surface temperature calculation in the SolEdge2D-EIRENE transport code

Julien Denis , B. Pégourié , J. Bucalossi , Hugo Bufferand , Guido Ciraolo et 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-01459103 v1
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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-04723407 v1

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-01550957 v1

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 cea-04738409 v1
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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-04747936 v1

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 et al.
Journal of Nuclear Materials, 2015, 463, pp.832-836. ⟨10.1016/j.jnucmat.2014.10.036⟩
Article dans une revue hal-01459177 v1
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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 Doceul et al.
Fusion Engineering and Design, 2014, 89 (9-10), pp.1928 - 1932. ⟨10.1016/j.fusengdes.2014.03.047⟩
Article dans une revue cea-04746730 v1

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 cea-04748647 v1
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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-04724821 v1

The WEST Project: Challenges of Diagnostic Integration

Sophie Salasca , Jerome Bucalossi , Emmanuelle Tsitrone , Christel Fenzi , Frank Samaille et al.
IEEE Transactions on Plasma Science, 2014, 42 (5), pp.1449-1456. ⟨10.1109/TPS.2014.2314648⟩
Article dans une revue cea-04748636 v1

Upgrades of the tore Supra water cooling system for the WEST project

A. Martinez , J. Bucalossi , M. Chantant , M. Missirlian , C. Portafaix et 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-04748788 v1

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 Visca et 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-04748480 v1

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-04738173 v1

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-04748556 v1

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-04738476 v1

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-04738422 v1
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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. Courtois et al.
Fusion Engineering and Design, 2013, 88 (9-10), pp.1818 - 1822. ⟨10.1016/j.fusengdes.2013.05.053⟩
Article dans une revue cea-04746748 v1

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 Lipa et 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-04748617 v1

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-01287089 v1
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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-04748467 v1
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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-04724831 v1
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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-04738280 v1
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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 et 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-04620308 v1
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Engineering studies for the installation of an axi-symmetric metallic divertor in Tore Supra

L. Doceul , C. Portafaix , J. Bucalossi , A. Saille , B. Bertrand et al.
Fusion Engineering and Design, 2011, 86 (9-11), pp.1660 - 1664. ⟨10.1016/j.fusengdes.2011.02.063⟩
Article dans une revue cea-04746374 v1
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The heat removal capability of actively cooled plasma-facing components for the ITER divertor

Marc Missirlian , M Richou , B Riccardi , P Gavila , T Loarer et al.
Physica Scripta, 2011, 2011 (T145), pp.014080. ⟨10.1088/0031-8949/2011/T145/014080⟩
Article dans une revue cea-04724810 v1
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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. Agarici et al.
Fusion Engineering and Design, 2011, 86 (4-5), pp.279 - 287. ⟨10.1016/j.fusengdes.2011.01.057⟩
Article dans une revue cea-04746912 v1
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Feasibility study of an actively cooled tungsten divertor in Tore Supra for ITER technology testing

J. Bucalossi , A. Argouarch , V. Basiuk , O. Baulaigue , P. Bayetti et al.
Fusion Engineering and Design, 2011, 86 (6-8), pp.684 - 688. ⟨10.1016/j.fusengdes.2011.01.114⟩
Article dans une revue cea-04746467 v1

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-04620224 v1

High heat flux testing of mock-ups for a full tungsten ITER divertor

P. Gavila , B. Riccardi , S. Constans , J.L. Jouvelot , I. Bobin Vastra et 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-04746682 v1
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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-04738307 v2
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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 Missirlian et al.
Physica Scripta, 2011, 85 (1), pp.015501. ⟨10.1088/0031-8949/85/01/015501⟩
Article dans une revue cea-04746429 v1

Characterization and damaging law of CFC for high heat flux actively cooled plasma facing components

G. Chevet , E. Martin , J. Boscary , G. Camus , V. Herb et al.
Journal of Nuclear Materials, 2011, 417 (1-3), pp.643-646. ⟨10.1016/j.jnucmat.2011.01.073⟩
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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. Achard et 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-04747486 v1

Fatigue lifetime of repaired high heat flux components for ITER divertor

M. Richou , M. Missirlian , B. Riccardi , P. Gavila , C. Desgranges et 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-04746452 v1
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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-04747878 v1

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. Cantone et 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-04748505 v1

Upgraded acceptance criteria from transient thermography control for the W7-X divertor target elements

Marc Missirlian , J. Boscary , R. Guigon , J. Schlosser , A. Durocher et 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-04724837 v1

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. Bej et al.
AIP Conference Proceedings, 2009, pp.435-438. ⟨10.1063/1.3273786⟩
Article dans une revue cea-04747920 v1

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 Camus et al.
Physica Scripta, 2009, T138 (014057), ⟨10.1088/0031-8949/2009/T138/014057⟩
Article dans une revue istex hal-00533365 v1
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Diagnostic systems on Tore Supra

C. Gil , C. de Michelis , D. Elbeze , C. Fenzi , J P Gunn et al.
Fusion Science and Technology, 2009, 56 (3), pp.1219 - 1252. ⟨10.13182/fst09-a9175⟩
Article dans une revue cea-04746344 v1
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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-04746876 v1
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Examination of W7-X target elements after high heat flux testing

Marc Missirlian , J. Boscary , A. Durocher , J. Schlosser , H. Greuner et al.
Journal of Nuclear Materials, 2009, 386-388, pp.856-859. ⟨10.1016/j.jnucmat.2008.12.269⟩
Article dans une revue istex hal-04620255 v1
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Advanced qualification methodology for actively cooled plasma facing components

Alain Durocher , Frederic Escourbiac , Andre Grosman , J. Boscary , Mario Merola et al.
Nuclear Fusion, 2008, 48 (7), pp.079801. ⟨10.1088/0029-5515/48/7/079801⟩
Article dans une revue cea-04731109 v1

Qualification of high heat flux components: application to target elements of W7-X divertor

Marc Missirlian , A Durocher , A Grosman , J Schlosser , J Boscary et al.
Physica Scripta, 2007, 2007 (T128), pp.182-188. ⟨10.1088/0031-8949/2007/T128/035⟩
Article dans une revue cea-04724800 v1
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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 et 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-04619995 v1
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Infrared thermography inspection methods applied to the target elements of W7-X divertor

Marc Missirlian , H Traxler , J Boscary , A Durocher , F Escourbiac et al.
Fusion Engineering and Design, 2007, 82 (15-24), pp.1747 - 1755. ⟨10.1016/j.fusengdes.2007.05.045⟩
Article dans une revue hal-04620361 v1

Infrared images data merging for plasma-facing component inspection

A. Durocher , J. Moysan , F. Escourbiac , M. Missirlian , N. Vignal et al.
Fusion Engineering and Design, 2007, 82 (15-24), pp.1694-1699. ⟨10.1016/j.fusengdes.2007.07.040⟩
Article dans une revue cea-04746845 v1
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Acceptance criteria for the ITER divertor vertical target

S. Fouquet , J. Schlosser , M. Merola , A. Durocher , F. Escourbiac et al.
Fusion Engineering and Design, 2006, 81 (1-7), pp.265 - 268. ⟨10.1016/j.fusengdes.2005.06.363⟩
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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. Bertrand et al.
Quantitative InfraRed Thermography Journal, 2005, 2 (1), pp.77-96. ⟨10.3166/qirt.2.77-96⟩
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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. Schedler et al.
Fusion Engineering and Design, 2005, 75-79, pp.387 - 390. ⟨10.1016/j.fusengdes.2005.06.328⟩
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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. Schlosser et al.
Fusion Engineering and Design, 2005, 75-79, pp.435-440. ⟨10.1016/j.fusengdes.2005.06.168⟩
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Tore-Supra infrared thermography system, a real steady-state diagnostic

D. Guilhem , J.L. Bondil , B. Bertrand , C. Desgranges , M. Lipa et 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-04748768 v1
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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-04746717 v1
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ITER-like PAM launcher for Tore Supra's LHCD system

J.H. Belo , Ph H Bibet , M. Missirlian , J. Achard , B. Beaumont et al.
Fusion Engineering and Design, 2005, 74 (1-4), pp.283 - 288. ⟨10.1016/j.fusengdes.2005.06.173⟩
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Thermal behaviour of redeposited layer under high heat flux exposure

E. Gauthier , S. Dumas , J. Matheus , M. Missirlian , Y. Corre et al.
Journal of Nuclear Materials, 2005, 337-339, pp.960 - 964. ⟨10.1016/j.jnucmat.2004.10.161⟩
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Flat Tile Armour Cooled by Hypervapotron Tube: a Possible Technology for ITER

J. Schlosser , F. Escourbiac , M. Merola , B. Schedler , P. Bayetti et al.
Physica Scripta, 2004, T111 (1), pp.199. ⟨10.1238/Physica.Topical.111a00199⟩
Article dans une revue cea-04746504 v1
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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-04620424 v1
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Design criteria for Tore Supra high heat flux components

Marc Missirlian , J Schlosser , M Lipa , R Mitteau , Ph Chappuis et al.
Fusion Engineering and Design, 2001, 56-57, pp.457-463. ⟨10.1016/S0920-3796(01)00327-1⟩
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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-03202608 v1
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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-01794678 v1

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-02866430 v1

Diagnostic integration issues in the Tore Supra upgrade project WEST

S. Salasca , J. Bucalossi , E. Tsitrone , C. Fenzi , F. Samaille et 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-04738544 v1
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ITER like lower hybrid passive active multi-junction antenna manufacturing

D. Guilhem , F. Samaille , B. Bertrand , M. Lipa , J. Achard et al.
2011 IEEE/NPSS 24th Symposium on Fusion Engineering, Jun 2011, Chicago, United States. ⟨10.1109/SOFE.2011.6052318⟩
Communication dans un congrès cea-04746892 v1

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. Portafaix et 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-04731134 v1