Search Results - "Duchateau, J.L."

New Considerations About Stability Margins of NbTi Cable in Conduit Conductors by Duchateau, J.L.

“…The design of NbTi cable in conduit conductors (CICCs) according to the criterion of the limiting current often leads to high copper content, with a Cu/nonCu…”
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Conductor Design of CS and EF Coils for JT-60SA by Kizu, K., Tsuchiya, K., Yoshida, K., Edaya, M., Ichige, T., Tamai, H., Matsukawa, M., della Corte, A., Di Zenobio, A., Muzzi, L., Turtu, S., Duchateau, J.L., Zani, L.

“…The conductor for central solenoid (CS) and equilibrium field (EF) coils of JT-60 Super Advanced (JT-60SA) were designed. The conductor for CS is Nb 3 Sn…”
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Discussion About the Size of a Future Fusion Demonstration Reactor: The Impact of the Toroidal Magnetic Field by Duchateau, J.L., Hertout, P., Johner, J.

“…In parallel to ITER preparation, power plant conceptual studies have been carried out in Europe as a guideline for the main design parameters of a fusion…”
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JT-60SA Toroidal Field Magnet System by Pizzuto, A., Semeraro, L., Zani, L., Bayetti, P., Cucchiaro, A., Decool, P., della Corte, A., Di Zenobio, A., Dolgetta, N., Duchateau, J.L., Fietz, W.H., Heller, R., Hertout, P., Kikuchi, M., Kizu, K., Lacroix, B., Muzzi, L., Nicollet, S., Polli, G.M., Portafaix, C., Reccia, L., Turtu, S., Verger, J.-M., Villari, R., Yoshida, K.

“…The broader approach agreement between Europe and Japan includes the construction of a fully superconducting tokamak, the JT-60 Super Advanced (JT-60SA), as a…”
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Dual channel cable in conduit thermohydraulics: Influence of some design parameters by Nicollet, S., Duchateau, J.L., Fillunger, H., Martinez, A., Parodi, S.

“…In the framework of the controlled nuclear fusion by magnetic confinement programme, a particular design of a Cable-in-Conduit Conductor (CICC) is being…”
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Evaluation of the current sharing temperature of the ITER Toroidal Field Model Coil by Heller, R., Ciazynski, D., Duchateau, J.L., Marchese, V., Savoldi-Richard, L., Zanino, R.

“…The construction and testing of the Toroidal Field Model Coil (TFMC) is part of one of the ITER large R&D projects. The main goal was to demonstrate the…”
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Inputs generation for COLISEUM coupling losses model using X-ray tomography: analytic and experimental approaches by Babouche, R., Zani, L., Louzguiti, A., Turck, B., Duchateau, J.L., Topin, F., Tiseanu, I., Lungu, M., Dumitru, D.

“…Tokamaks coils are wound with long lengths of cables including hundreds of superconducting and copper strands twisted together into multiple stages. They refer…”
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Heat deposition in the ITER FEAT poloidal field coils during a plasma scenario by Hertout, P., Bessette, D., Bleyer, A., Duchateau, J.L., Nicollet, S.

“…During the last phase of the EDA (Engineering Design Activities) of the ITER (International Thermonuclear Experimental Reactor) project, a fully…”
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AC Losses Calculations for the ITER CS and PF Magnet Systems during Plasma Operation by Bauer, P., Breschi, M., Cavallucci, L., Duchateau, J.L., Gauthier, F., Ilyin, Y., Schild, T., Torre, A., Turck, B.

“…While the ITER magnet system assembly is progressing, models are being developed to predict the performances of the coils in support of the preparation of…”
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Test results and analysis of two European full-size conductor samples for ITER by Ciazynski, D., Duchateau, J.L., Schild, T., Fuchs, A.M.

“…The European Home Team is responsible for the design, the fabrication and the test of the Toroidal Field Model Coil (TFMC) of the International Thermonuclear…”
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Model of heat deposition during fast discharge tests of the ITER toroidal field model coil by Hertout, P., Bleyer, A., Duchateau, J.L., Martinez, A., Nicollet, S.

“…In the framework of the ITER (International Thermonuclear Experimental Reactor) project, the TFMC (Toroidal Field Model Coil) has been manufactured by European…”
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Eddy current and thermal analysis of the TF model coil during safety discharges by Hertout, P., Duchateau, J.L., Martinez, A.

“…The Toroidal Field Model Coil (TFMC) has been manufactured by European industry since 1997 in the frame of the International Thermonuclear Experimental Reactor…”
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Current distribution and strain influence on the electromagnetic performance of the CS Insert by Galindo, V., Ciazynski, D., Duchateau, J.L., Nishijima, G., Koizumi, N., Takahashi, Y., Ando, T.

“…The Central Solenoid Model Coil (CSMC) is a solenoid consisting of 18 concentric layers, wound with Nb/sub 3/Sn cable-in-conduit conductor, jacketed with…”
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Resistances of electrical joints in the TF model coil of ITER: comparisons of first test results with samples results by Ciazynski, D., Ricci, M., Duchateau, J.L., Marchese, V., Ulbricht, A., Wuechner, F., Zahn, G., Fillunger, H., Maix, R.

“…The test of the Toroidal Field (TF) Model Coil of the International Thermonuclear Experimental Reactor (ITER) has been the opportunity to measure the DC…”
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Optimisation of the magnet system of a 200 MW steady state tokamak by Duchateau, J.L., Albajar, F., Ane, J.M., Bottereau, J.M., Bottiglioni, F., Hertout, P., Johner, J., Magaud, Ph, Turck, B., Zabiego, M.

“…A study was undertaken to outline a long pulse D-T tokamak dedicated to plasma physics close to reactor conditions but still operating at limited values of…”
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ITER Side Correction Coil Quench model and analysis by Nicollet, S., Bessette, D., Ciazynski, D., Duchateau, J.L., Gauthier, F., Lacroix, B.

“…•Quench thermo-hydraulic studies on the ITER Side Correction Coil.•Model with SuperMagnet Code with four parallel pancakes and one cryogenic…”
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Using the HELIOS facility for assessment of bundle-jacket thermal coupling in a CICC by Lacroix, B., Rousset, B., Cloez, H., Decool, P., Duchateau, J.L., Hoa, C., Luchier, N., Nicollet, S., Topin, F.

“…•An experiment was performed for assessing bundle-jacket thermal coupling in a CICC.•The mock-up was made of an ITER TF conductor equipped with Cu sleeves and…”
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AC losses and current distribution in 40 kA NbTi and Nb/sub 3/Sn conductors for NET/ITER by Ciazynski, D., Turck, B., Duchateau, J.L., Meuris, C.

“…General working formulas usable for calculations of AC losses in superconducting multistage twisted cables have been developed. In situ contact resistances…”
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Quench characterization and thermo hydraulic analysis of SST-1 TF magnet busbar by Sharma, A.N., Pradhan, S., Duchateau, J.L., Khristi, Y., Prasad, U., Doshi, K., Varmora, P., Tanna, V.L., Patel, D., Panchal, A.

“…•Details of SST-1 TF busbar quench detection.•Simulation of slow propagating normal zone.•Thermo hydraulic analyses of TF busbar in current feeder system…”
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Thermo hydraulic and quench propagation characteristics of SST-1 TF coil by Sharma, A.N., Pradhan, S., Duchateau, J.L., Khristi, Y., Prasad, U., Doshi, K., Varmora, P., Patel, D., Tanna, V.L.

“…•Details of SST-1 TF coils, CICC.•Details of SST-1 TF coil cold test.•Quench analysis of TF magnet.•Flow changes following quench.•Predictive analysis of…”
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