Search Results - "Samaille, F"

The WEST project: Testing ITER divertor high heat flux component technology in a steady state tokamak environment by Bucalossi, J., Missirlian, M., Moreau, P., Samaille, F., Tsitrone, E., van Houtte, D., Batal, T., Bourdelle, C., Chantant, M., Corre, Y., Courtois, X., Delpech, L., Doceul, L., Douai, D., Dougnac, H., Faïsse, F., Fenzi, C., Ferlay, F., Firdaouss, M., Gargiulo, L., Garin, P., Gil, C., Grosman, A., Guilhem, D., Gunn, J., Hernandez, C., Keller, D., Larroque, S., Leroux, F., Lipa, M., Lotte, P., Martinez, A., Meyer, O., Micolon, F., Mollard, P., Nardon, E., Nouailletas, R., Pilia, A., Richou, M., Salasca, S., Travère, J.-M.

“…The WEST project recently launched at Cadarache consists in transforming Tore Supra in an X-point divertor configuration while extending its long pulse…”
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Manufacturing and characterization of stainless steel/CuCrZr and stainless steel/Cu junction ring by explosive welding method by Firdaouss, M., Diez, M., Samaille, F.

“…The most common material for heat sink used in actively cooled plasma facing components is CuCrZr, which is not easily welded to steel used for cooling pipes…”
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Overview of the different processes of tungsten coating implemented into WEST tokamak by Firdaouss, M., Desgranges, C., Hernandez, C., Richou, M., Greuner, H., Böswirth, B., Zacharie-Aubrun, I., Blay, T., Bucalossi, J., Missirlian, M., Samaille, F., Tsitrone, E.

“…The Tore Supra tokamak is being transformed in an x-point divertor fusion device within the frame of the WEST (W-for tungsten-Environment in Steady-state…”
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Leak tightness tests on actively cooled plasma facing components: Lessons learned from Tore Supra experience and perspectives for the new fusion machines by Chantant, M., Lambert, R., Gargiulo, L., Hatchressian, J.-C., Guilhem, D., Samaille, F., Soler, B.

“…•Test procedures for the qualification of the tightness of actively cooled plasma facing components were defined.•The test is performed after the component…”
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Mechanical analysis of WEST divertor support plate by Batal, T., Ferlay, F., Burles, S., Larroque, S., Doceul, L., Samaille, F., Missirlian, M., Bucalossi, J.

“…•Disruption’s torque in the PFC and support plate was simulated thanks to ANSYS.•Three load cases were studied: one in steady states and one in VDE.•The ANSYS…”
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Tungsten coating by ATC plasma spraying on CFC for WEST tokamak by Firdaouss, M, Desgranges, C, Hernandez, C, Mateus, C, Maier, H, Böswirth, B, Greuner, H, Samaille, F, Bucalossi, J, Missirlian, M

“…In the field of fusion experiments using a tokamak, the plasma facing components (PFC) are the closest object to the hot plasma. Due to the plasma-wall…”
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Study of the pores inside tungsten coating after thermal cycling for fusion device by Desgranges, C, Firdaouss, M, Hernandez, C, Martin, C, Ruset, C, Grigore, E, Missirlian, M, Samaille, F, Bucalossi, J

“…In the next fusion devices, all the plasma facing components will consist of bulk tungsten or tungsten coating on carbon. This paper focuses on the behaviour…”
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Feasibility study of an actively cooled tungsten divertor in Tore Supra for ITER technology testing by Bucalossi, J., Argouarch, A., Basiuk, V., Baulaigue, O., Bayetti, P., Bécoulet, M., Bertrand, B., S. Brémond, Cara, P., Chantant, M., Corre, Y., Courtois, X., Doceul, L., Ekedahl, A., Faisse, F., M. Firdaouss, Garcia, J., Gargiulo, L., Gil, C., Grisolia, C., Gunn, J., Hacquin, S., Hertout, P., Huysmans, G., Imbeaux, F., Jiolat, G., Joanny, M., Jourd’heuil, L., Jouve, M., Kukushkin, A., Lipa, M., Lisgo, S., Loarer, T., Maget, P., Magne, R., Marandet, Y., Martinez, A., Mazon, D., Meyer, O., Missirlian, M., Monier-Garbet, P., Moreau, P., Nardon, E., Panayotis, S., Pégourié, B., Pitts, R.A., Portafaix, C., Richou, M., Sabot, R., Saille, A., Saint-Laurent, F., Samaille, F., Simonin, A., Tsitrone, E.

“…In order to reduce the risks for ITER Plasma Facing Components (PFCs), it is proposed to equip Tore Supra with a full tungsten divertor, benefitting from the…”
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Test of fiber optic based current sensors on the Tore Supra tokamak by Moreau, Ph, Brichard, B., Fil, A., Malard, Ph, Pastor, P., Le-Luyer, A., Samaille, F., Massaut, V.

“…Fiber optic current sensors have been recently considered for current measurements in ITER. These sensors exploit Ampere's law by measuring the change of light…”
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The WEST project: validation program for WEST tungsten coated plasma facing components by Richou, M, Missirlian, M, Tsitrone, E, Bucalossi, J, Desgranges, C, Firdaouss, M, Guilhem, D, Greuner, H, Hernandez, C, Lipa, M, Pintsuk, G, Samaille, F

“…The W-for tungsten-Environment in Steady-state Tokamak (WEST) project is based on an upgrade of the Tore Supra tokamak from a carbon limiter to an X-point…”
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Tungsten covered graphite and copper elements and ITER-like actively cooled tungsten divertor plasma facing units for the WEST project by Guilhem, D, Bucalossi, J, Burles, S, Corre, Y, Ferlay, F, Firdaouss, M, Languille, P, Lipa, M, Martinez, A, Missirlian, M, Proust, M, Richou, M, Samaille, F, Tsitrone, E

“…After a brief introduction giving some insight of the WEST project, we present the three types of plasma facing units (PFUs) developed for the WEST project…”
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Overview of the deuterium inventory campaign in Tore Supra: Operational conditions and particle balance by Pégourié, B., Brosset, C., Tsitrone, E., Beauté, A., Brémond, S., Bucalossi, J., Carpentier, S., Corre, Y., Delchambre, E., Desgranges, C., Devynck, P., Douai, D., Dunand, G., Ekedahl, A., Escarguel, A., Gauthier, E., Gunn, J.P., Hertout, P., Hong, S.-H., Kazarian, F., Kočan, M., Linez, F., Marandet, Y., Martinez, A., Mayer, M., Meyer, O., Monier-Garbet, P., Moreau, P., Oddon, P., Pascal, J.-Y., Rimini, F., Roth, J., Saint-Laurent, F., Samaille, F., Vartanian, S., Arnas, C., Aréou, E., Gil, C., Lasalle, J., Manenc, L., Martin, C., Richou, M., Roubin, P., Sabot, R.

“…A specific experiment was performed in Tore Supra, dedicated to the search for consistency between wall inventories estimated from gas balance and post-mortem…”
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The WEST project mechanical analysis of the divertor structure according to the nuclear construction code by Larroque, S., Portafaix, C., Saille, A., Doceul, L., Bucalossi, J., Samaille, F., de Freslon, S.

“…•Divertor structure is mainly loaded by electromagnetical forces.•A simplified FEM analysis give the stresses in the structure.•RCCM criteria are required for…”
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Upgrades of the tore Supra water cooling system for the WEST project by Martinez, A., P.Bayetti, Bucalossi, J., Chantant, M., Missirlian, M., Portafaix, C., Samaille, F.

“…•Thermo-hydraulic studies of plasma facing components.•Design of a PHTS.•Design studies of a tokamak cooling system. In ITER, it is foreseen to use an…”
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Design, integration and feasibility studies of the Tore-Supra West divertor structure by Doceul, L., Bucalossi, J., Larroque, S., Lipa, M., Portafaix, C., Saille, A., Samaille, F., Soler, B., Ferlay, F., Verger, J.M.

“…Actively cooled tungsten plasma facing components will be used in the ITER divertor. In order to fully validate such a technology (industrial manufacturing,…”
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Steady state long pulse tokamak operation using Lower Hybrid Current Drive by Bécoulet, A., Hoang, G.T., Artaud, J.F., Bae, Y.S., Belo, J., Berger-By, G., Bernard, J.M., Cara, Ph, Cardinali, A., Castaldo, C., Ceccuzzi, S., Cesario, R., Cho, M.H., Decker, J., Delpech, L., Do, H.J., Ekedahl, A., Garcia, J., Garibaldi, P., Goniche, M., Guilhem, D., Hamlyn-Harris, C., Hillairet, J., Huang, Q.Y., Imbeaux, F., Jia, H., Kazarian, F., Kim, S.H., Lausenaz, Y., Litaudon, X., Maggiora, R., Magne, R., Marfisi, L., Meschino, S., Milanesio, D., Mirizzi, F., Mollard, P., Namkung, W., Pajewski, L., Panaccione, L., Park, S., Park, H., Peysson, Y., Saille, A., Samaille, F., Schettini, G., Schneider, M., Sharma, P.K., Tuccillo, A., Tudisco, O., Vecchi, G., Villari, R., Vulliez, K., Wu, Y., Yang, H.L., Zeng, Q.

“…Steady-state long pulse operation of tokamaks requires fully non-inductive current drive, thus an external current drive method. Lower Hybrid Current Drive is…”
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Design and test program of a simplified divertor dummy coil structure for the WEST project by Doceul, L., Bucalossi, J., Dougnac, H., Ferlay, F., Gargiulo, L., Keller, D., Larroque, S., Lipa, M., Pilia, A., Portafaix, C., Saille, A., Salami, M., Samaille, F., Soler, B., Thouvenin, D., Verger, J.M., Zago, B.

“…•The mechanical design and integration of the divertor structure has been performed.•The design of the casing and the winding-pack has been finalized.•The coil…”
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Computation of Tore Supra cooling system limits by Chantant, M., Bayetti, P., Bucalossi, J., Delpech, L., Ekedahl, A., Geraud, A., Guilhem, D., Mollard, P., Samaille, F., Thouvenin, D.

“…► 1D transient thermal–hydraulic analysis of a tokamak cooling system. ► Validation of the computed data on measurements. ► Design of a cooling system. Tore…”
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New high power CW test facilities for ITER ICRH components testing by Bernard, J.M., Lombard, G., Argouarch, A., Chaix, J.P., Fejoz, P., Garibaldi, P., Hatchressian, J.C., Lebourg, P., Martinez, A., Mollard, P., Mougeolle, G., Noel, F., Saille, A., Samaille, F., Soler, B., Thouvenin, D., Volpe, D., Vulliez, K.

“…First CW test bed, devoted for ion cyclotron resonance heating (ICRH), is being built at CEA Cadarache. It has been designed for testing the ICRH antenna sub…”
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Engineering studies for the installation of an axi-symmetric metallic divertor in Tore Supra by Doceul, L., Portafaix, C., Bucalossi, J., Saille, A., Bertrand, B., Lipa, M., Missirlian, M., G.Jiolat, Samaille, F., Soler, B.

“…Tore Supra (TS) has been designed to operate using technologies that allow long plasma operation (a few minutes), by means of superconducting magnets and…”
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