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    Join us !
    IRFM welcomes around 30 PhD students and 40 trainees per year.
  • darkblurbg
    WEST Tokamak

    W (tungsten) Environment in Steady-state Tokamak
    WEST validates and fatigue-tests the ITER actively-cooled tungsten divertor components
    during the ITER construction phase and prepare their safe operation.

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    IRFM activities
    Participating in the realization of ITER and European Fusion program
    Preparing the operation of next generation devices
    Fusion physics understanding by theory and experiments
    Fusion Reactor Studies
    And Much More...

Institute for Magnetic Fusion Research

IRFM is an institute of CEA, the French Alternatives Energies and Atomic Energy Commission. Located in the CEA Cadarache Centre, with ITER next door, the 200+ physicists, engineers and technicians of the Institute carry out research on Magnetic Fusion as a potential future energy source.

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IRFM Activities

Project Iter

Contribute to the implementation of the ITER project and those of the “Broader Approach”

Experiment, control, theory and modelling

Prepare the scientific operation of ITER, through control and experimentation activities, and through theory and modeling,

Future fusion reactor

Establish the basis for future fusion reactor.

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300

Employees

25

Collaborators

27

Ph-D

190 +

Publications/year

Latest publications

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, J Bucalossi, C Brun, Y Corre, E Delmas, H Greuner, B Guillermin, J Gunn, J Hatchressian, R Jalageas, Q Li, M Lipa, M Lozano, G Luo, C Pocheau, H Roche, E Tsitrone, N Vignal, W Wang, A Saille, B Zago

2024-07-15

Fusion Engineering and Design, 2023, 193, pp.113683. ⟨10.1016/j.fusengdes.2023.11368320⟩

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, M. Lipa, B. Boeswirth, J. Boscary

2024-07-09

Fusion Engineering and Design, 2011, 86 (9-11), pp.1579-1582. ⟨10.1016/j.fusengdes.2011.03.113⟩

Pharmacokinetic Drug-Drug Interaction of Calcium Channel Blockers With Cyclosporine in Hematopoietic Stem Cell Transplant Children

Elodie Bernard, Sylvain Goutelle, Yves Bertrand, Nathalie Bleyzac

2024-07-08

Annals of Pharmacotherapy, 2014, 48 (12), pp.1580-1584. ⟨10.1177/1060028014550644⟩

Suprapubic versus transurethral catheterization for bladder drainage in male rectal cancer surgery (GRECCAR10), a randomized clinical trial

B. Trilling, F. Tidadini, Z. Lakkis, M. Jafari, A. Germain, E. Rullier, J. Lefevre, J. Tuech, A. Kartheuser, D. Leonard, M. Prudhomme, G. Piessen, J. Regimbeau, E. Cotte, D. Duprez, B. Badic, Y. Panis, M. Rivoire, B. Meunier, G. Portier, J. Bosson, A. Vilotitch, A. Foote, Y. Caspar, P. Rouanet, J. Faucheron

2024-07-04

Techniques in Coloproctology, 2024, 28 (1), pp.77. ⟨10.1007/s10151-024-02950-2⟩

Overview of ITPA R&D diagnostics activities in support of the ITER research plan

D Mazon, S Zoletnik, G Vayakis, G Yun, H Liu

2024-07-03

HTPD 2024 - 25th Topical Conference on High Temperature Plasma Diagnostics, Apr 2024, Asheville, United States

The WEST Thomson scattering diagnostic: plasma core measurement

G Colledani, R Sabot, L Schiesko, N Fedorczak, M Carole, G Moureau, S Vives, A Bec, L Doceul, F Faïsse, C Bouchand, Y Moudden, P Blanchard, P Bilkova, P Bohm, E. Pash, R. Scannell, B. Habart

2024-07-03

HTPD 2024 - 25th Topical Conference on High Temperature Plasma Diagnostics, Apr 2024, Asheville, United States.

Modelling of radio frequency sheath and fast wave coupling on the realistic ion cyclotron resonant antenna surroundings and the outer wall

L. Lu, L. Colas, J. Jacquot, Bruno Després, Stéphane Heuraux, E. Faudot, D. van Eester, K. Crombé, A. Krivska, J.-M. Noterdaeme, Walid Helou, Julien Hillairet

2024-07-02

Plasma Physics and Controlled Fusion, 2018, 60, pp.035003. ⟨10.1088/1361-6587/aaa030⟩

Methodology for the design of diagnostic windows for Tore Supra

Marc Missirlian, M Lipa, C Portafaix, C Gil, G Rey

2024-06-25

Fusion Engineering and Design, 2003, 66-68, pp.911 - 917. ⟨10.1016/s0920-3796(03)00375-2⟩

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

Marc Missirlian, H Traxler, J Boscary, A Durocher, F Escourbiac, J Schlosser, B Schedler, P Schuler

2024-06-25

Fusion Engineering and Design, 2007, 82 (15-24), pp.1747 - 1755. ⟨10.1016/j.fusengdes.2007.05.045⟩

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

Marc Missirlian, J. Boscary, A. Durocher, J. Schlosser, H. Greuner, L.S. Sigl

2024-06-21

Journal of Nuclear Materials, 2009, 386-388, pp.856-859. ⟨10.1016/j.jnucmat.2008.12.269⟩