Search Results - "Pocheau, C"

An ITER Challenge Absolute Surface Temperature Measurements of Low and Varying Emissivity Tungsten Plasma-Facing Components by Guilhem, D., Gaspar, J., Pocheau, C., Corre, Y.

“…One of the challenges that International Thermonuclear Experimental Reactor (ITER) will face during plasma operation is to determine the absolute divertor…”
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Emissivity measurement of tungsten plasma facing components of the WEST tokamak by Gaspar, J., Pocheau, C., Corre, Y., Ehret, N., Guilhem, D., Houry, M., Loarer, T., Loewenhoff, Th, Martin, C., Pardanaud, C., Pintsuk, G., Richou, M., Rigollet, F., Roche, H., Sepulcre, G., Wirtz, M.

“…Since tungsten (W) has been selected as material for the ITER divertor target the knowledge of the emissivity in the infrared (IR) wavelength range becomes…”
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Full coverage infrared thermography diagnostic for WEST machine protection by Courtois, X., Aumeunier, MH, Balorin, C., Migozzi, J.B., Houry, M., Blanckaert, K., Moudden, Y., Pocheau, C., Saille, A., Hugot, E., Marcos, M., Vives, S.

“…The WEST platform aims at testing ITER like W divertor targets in an integrated tokamak environment. To operate long plasma discharges, IR thermography is…”
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Manufacturing, testing and installation of the full tungsten actively cooled ITER-like divertor in the WEST tokamak by Missirlian, M., Firdaouss, M., Richou, M., Hernandez, C., Gargiulo, L., Bucalossi, J., Brun, C., Corre, Y., Delmas, E., Greuner, H., Guillermin, B., Gunn, J., Hatchressian, J.C., Jalageas, R., Li, Q., Lipa, M., Lozano, M., Luo, G., Pocheau, C., Roche, H., Tsitrone, E., Vignal, N., Wang, W., Saille, A., Zago, B.

“…•We presented the WEST full tungsten actively cooled divertor, mentioning its relevance with the ITER one.•Main features including key elements related to the…”
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In-situ assessment of the emissivity of tungsten plasma facing components of the WEST tokamak by Gaspar, J., Aumeunier, M.-H., Le Bohec, M., Rigollet, F., Brezinsek, S., Corre, Y., Courtois, X., Dejarnac, R., Diez, M., Dubus, L., Fedorczak, N., Houry, M., Moncada, V., Moreau, P., Pocheau, C., Talatizi, C., Tsitrone, E.

“…•In-situ method to measure the plasma facing components emissivity.•Non-uniform emissivity measured along the divertor W-coated components.•Implication of…”
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The very high spatial resolution infrared thermography on ITER-like tungsten monoblocks in WEST Tokamak by Houry, M., Pocheau, C., Aumeunier, M-H., Balorin, C., Blanckaert, K., Corre, Y., Courtois, X., Ferlay, F., Gaspar, J., Gazzotti, S., Grosjean, A., Loarer, Th, Roche, H., Saille, A., Vives, S.

“…A new Infrared diagnostic has been developed by CEA-IRFM and installed in the WEST tokamak to measure surface temperature of the actively cooled W-monoblocks…”
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First heat flux estimation in the lower divertor of WEST with embedded thermal measurements by Gaspar, J., Corre, Y., Firdaouss, M., Gardarein, J.L., Gerardin, J., Gunn, J.P., Houry, M., Laffont, G., Loarer, T., Missirlian, M., Morales, J., Moreau, P., Pocheau, C., Tsitrone, E.

“…The present paper deals with the surface heat flux estimation with thermocouples (TC) and fiber Bragg grating (FBG) embedded in the plasma facing components…”
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Sustained W-melting experiments on actively cooled ITER-like plasma facing unit in WEST by Corre, Y, Grosjean, A, Gunn, J P, Krieger, K, Ratynskaia, S, Skalli-Fettachi, O, Bourdelle, C, Brezinsek, S, Bruno, V, Chanet, N, Coenen, J, Courtois, X, Dejarnac, R, Delmas, E, Delpech, L, Desgranges, C, Diez, M, Dubus, L, Durif, A, Ekedahl, A, Fedorczak, N, Firdaouss, M, Gardarein, J-L, Gaspar, J, Gerardin, J, Guillemaut, C, Houry, M, Loarer, T, Maget, P, Mandelbaum, P, Mitteau, R, Missirlian, M, Moreau, P, Nouailletas, R, Nardon, E, Pocheau, C, Podolnik, A, Reilhac, P, Regal-Mezin, X, Reux, C, Richou, M, Rigollet, F, Schwob, J-L, Thorén, E, Tolias, P, Tsitrone, E

“…Abstract The consequences of tungsten (W) melting on divertor lifetime and plasma operation are high priority issues for ITER. Sustained and controlled…”
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First temperature database achieved with Fiber Bragg Grating sensors in uncooled plasma facing components of the WEST lower divertor by Corre, Y., Chanet, N., Cotillard, R., Gaspar, J., Laffont, G., Pocheau, C., Caulier, G., Destouches, C., Gardarein, J-L., Firdaouss, M., Houry, M., Missirlian, M., Roussel, N., Santraine, B.

“…Plasma Facing Components (PFCs) temperature measurement is required to ensure safe high power for long pulse tokamak operation and for physics studies. A set…”
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Design and integration of femtosecond Fiber Bragg gratings temperature probes inside actively cooled ITER-like plasma-facing components by Chanet, N., Corre, Y., Cotillard, R., Gaspar, J., Laffont, G., Pocheau, C., Caulier, G., Dechelle, C., De Gentile, B., Destouches, C., Dubus, L., Gallay, F., Hernandez, C., Missirlian, M., Richou, M., Roussel, N., Santraine, B.

“…Measuring the temperature in plasma-facing components (PFCs) provides information both on plasma parameters in the divertor region and on the thermal stress…”
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Interpretation of temperature distribution observed on W-ITER-like PFUs in WEST monitored with a very-high-resolution IR system by Grosjean, A., Aumeunier, M.H., Corre, Y., Firdaouss, M., Gaspar, J., Gerardin, J., Gunn, J.P., Courtois, X., Dejarnac, R., Diez, M., Dubus, L., Houry, M., Pocheau, C., Tsitrone, E.

“…During the 2019 experimental campaign, the WEST tokamak was partially equipped with ITER-like plasma facing units (PFUs) made of discrete monoblocks (MBs) in…”
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Very high-resolution infrared imagery of misaligned tungsten monoblock edge heating in the WEST tokamak by Grosjean, A., Corre, Y., Gaspar, J., Gunn, J.P., Carpentier, S., Courtois, X., Dejarnac, R., Delmas, E., De Temmerman, G., Diez, M., Dubus, L., Dupont, L., Escourbiac, F., Firdaouss, M., Gerardin, J., Houry, M., Pitts, R., Pocheau, C., Tsitrone, E.

“…Fourteen ITER-like plasma-facing units (PFUs) made of bulk tungsten were installed in the WEST tokamak divertor. Five of which were misaligned with their…”
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Thermal behavior and temperature measurements of melting beryllium plasma-facing components exposed to high heat flux by Gauthier, E., Pocheau, C., Kovari, M., Barnard, J.M., Crowley, B., Godwin, J., Lane, C.

“…The emissivity of metallic materials is low and varies with temperature and wavelength inducing errors on surface temperature measurements. High heat flux…”
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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 by Gaspar, J., Rigollet, F., Ehret, N., Anquetin, Y., Bernard, E., Corre, Y., Diez, M., Firdaouss, M., Houry, M., Loarer, T., Martin, C., Missirlian, M., Moreau, P., Pocheau, C., Reihlac, P., Richou, M., Tsitrone, E.

“…•Emissivity variability for a serial production of ITER-like divertor components.•Emissivity evolution due to high heat flux tests.•Non-uniform emissivity…”
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Operational limits on WEST inertial divertor sector during the early phase experiment by Firdaouss, M, Corre, Y, Languille, P, Greuner, H, Autissier, E, Desgranges, C, Guilhem, D, Gunn, J P, Lipa, M, Missirlian, M, Pascal, J-Y, Pocheau, C, Richou, M, Tsitrone, E

“…The primary goal of the WEST project is to be a test bed to characterize the fatigue and lifetime of ITER-like W divertor components subjected to relevant…”
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Surface heat flux estimation with embedded fiber Bragg gratings measurements: Numerical study by Gaspar, J., Corre, Y., Gardarein, J-L., Firdaouss, M., Guilhem, D., Houry, M., Laffont, G., Niliot, C. Le, Missirlian, M., Pocheau, C., Rigollet, F.

“…•Synthetic Bragg Gratings temperature measurements for WEST plasma scenario (close and far X points)•Heat flux estimation done with 2D nonlinear unsteady…”
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Development of a Laser Ablation System Kit (LASK) for Tokamak in vessel tritium and dust inventory control by Hernandez, C., Roche, H., Pocheau, C., Grisolia, C., Gargiulo, L., Semerok, A., Vatry, A., Delaporte, P., Mercadier, L.

“…During Tokamak operation, Plasma Facing Components (PFCs) are subjected to severe interaction with plasma. As a consequence and independently of the PFCs…”
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Infrared reflection properties and modelling of in situ reflection measurements on plasma-facing materials in Tore Supra by Reichle, R, Lasserre, J-P, Oelhoffen, F, Desgranges, C, Faisse, F, Eupherte, L, Pocheau, C, Todeschini, M

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Concept and development of ITER divertor thermography diagnostic by Reichle, R., Andrew, Ph, Balorin, C., Brichard, B., Carpentier, S., Corre, Y., Davi, M., Daviot, R., Desgranges, C., Gardarein, J.L., Gauthier, E., Guilhem, D., Gicquel, S., Herrmann, A., Hernandez, D., Jouve, M., Le Niliot, Ch, Loarer, Th, Martin, A., Martins, J.P., Migozzi, J.-B., Patterlini, J.P., Pocheau, C., Rigollet, F., Roche, H., Travere, J.M.

“…The conceptual and technological development of ITER divertor thermography approaches the aim to provide measurements for machine protection and physics…”
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Optimization of laser ablation technique for deposited layer removal on carbon plasma facing components by Roche, H., Courtois, X., Delaporte, Ph, Dittmar, T., Farcage, D., Gauthier, E., Hernandez, C., Languille, P., Loarer, T., Mercadier, L., Naiim Habib, M., Pascal, J.-Y., Pocheau, C., Semerok, A., Tsitrone, E., Vignal, N., Grisolia, C.

“…A laser ablation technique has been adapted for removal of the deposited layers on carbon plasma facing components from Tore Supra. This paper describes in…”
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