Search Results - "Salavy, J.F"

R&D issues for SiCf/SiC composites structural material in fusion power reactor blankets by GIANCARLI, L, AIELLO, G, CASO, A, GASSE, A, LE MAROIS, G, POITEVIN, Y, SALAVY, J. F, SZCZEPANSKI, J

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HCLL TBM design status and development by Aiello, G., de Dinechin, G., Forest, L., Gabriel, F., Puma, A. Li, Rampal, G., Rigal, E., Salavy, J.F., Simon, H.

“…The Helium Cooled Lithium Lead Test Blanket Module (HCLL-TBM) is one of the two European TBMs, representative of DEMO blanket technology, that shall be ready…”
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European testing blanket modules auxiliaries design by Aiello, A., Ciampichetti, A., Cismondi, F., Ghidersa, B.E., Ilkei, Tamas, Kosek, L., Salavy, J.F.

“…The design of the auxiliary systems for the two European Test Blanket Modules is an important engineering task that will allow the successful integration of…”
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The ancillary systems of the European test blanket modules: Configuration and integration in TIER by Ricapito, I., Bede, O., Boccaccini, L.V., Ciampichetti, A., Ghidersa, B., Guerrini, L., Lässer, R., Neuberger, H., Poitevin, Y., Salavy, J.F.

“…The conceptual design of the ancillary systems of the European Test Blanket Modules (TBMs), namely the PbLi circuit, the Helium Cooling Systems (HCSs), the…”
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Failure mode and effect analysis for the European test blanket modules by Pinna, T., Boccaccini, L.V., Salavy, J.F.

“…A failure mode and effect analysis (FMEA) at component level was done to study possible safety relevant implications arising from failures in European test…”
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A 2D finite element modelling of tritium permeation for the HCLL DEMO blanket module by Gabriel, F., Escuriol, Y., Dabbene, F., Gastaldi, O., Salavy, J.F., Giancarli, L.

“…A local finite element modelling of the tritium permeation through the HCLL breeder unit cooling plates is presented. The tritium concentration in the helium…”
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Blanket manufacturing technologies: Thermomechanical tests on helium cooled lithium lead (HCLL) blanket mocks up by Laffont, G., Cachon, L., Taraud, P., Challet, F., Rampal, G., Rigal, E., Salavy, J.F., Poitevin, Y.

“…In the Helium Cooled Lithium Lead (HCLL) blanket concept, the lithium lead plays the double role of breeder and multiplier material, and the helium is used as…”
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Design requirements for SiC/SiC composites structural material in fusion power reactor blankets by Giancarli, L, Bonal, J.P, Caso, A, Le Marois, G, Morley, N.B, Salavy, J.F

“…This paper recalls the main features of the TAURO blanket, a self-cooled Pb-17Li concept using SiC/SiC composites as structural material, developed for FPR…”
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Design approach for the main ITER test blanket modules for the EU helium cooled lithium–lead blankets by Rampal, G., Gatelet, D., Giancarli, L., Laffont, G., Li-Puma, A., Salavy, J.F., Rigal, E.

“…One of the two blanket concepts developed by the EU for testing in ITER is the helium cooled lithium–lead (HCLL) concept. Four types of HCLL test blanket…”
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Conceptual design of a high temperature water-cooled divertor for a fusion power reactor by Giancarli, L., Bonal, J.P., Puma, A. Li, Michel, B., Sardain, P., Salavy, J.F.

“…This paper presents the conceptual design of a water-cooled divertor target using EUROFER as structural material, water coolant pressure and outlet…”
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The EU advanced lead lithium blanket concept using SiCf/SiC flow channel inserts as electrical and thermal insulators by NORAJITRA, P, BÜHLER, L, SALAVY, J. F, FISCHER, U, KLEEFELDT, K, MALANG, S, REIMANN, G, SCHNAUDER, H, GIANCARLI, L, GOLFIER, H, POITEVIN, Y

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European achievements for ITER high heat flux components by Merola, M, Vieider, G, Bet, M, Bobin Vastra, I, Briottet, L, Chappuis, P, Cheyne, K, Dell'Orco, G, Duglué, D, Duwe, R, Erskine, S, Escourbiac, F, Fèbvre, M, Grattarola, M, Moreschi, F, Orsini, A, Pamato, R, Petrizzi, L, Plöchl, L, Riccardi, B, Rigal, E, Rödig, M, Salavy, J.F, Schedler, B, Schlosser, J, Tähtinen, S, Vesprini, R, Visca, E, Wu, C.H

“…This paper summarises the main activities carried out by the EU Home Team to develop suitable solutions for the ITER high heat flux components, namely the…”
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Tauro: a ceramic composite structural material self-cooled Pb—17Li breeder blanket concept by Ramírez, A.S. Pérez, Caso, A., Giancarli, L., Le Bars, N., Chaumat, G., Salavy, J.F., Szczepanski, J.

“…The use of a low-activation (LA) ceramic composite (CC) as structural material appears essential to demonstrate the potential of fusion power reactors for…”
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Evaluation of divertor conceptual designs for a fusion power plant by Ferrari, M., Giancarli, L., Kleefeldt, K., Nardi, C., Rödig, M., Reimann, J., Salavy, J.F.

“…In the frame of the preliminary study of plants suitable for the energy production from the fusion power, particular emphasis has been given on the divertor…”
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R&D issues for SiC f/SiC composites structural material in fusion power reactor blankets by Giancarli, L, Aiello, G, Caso, A, Gasse, A, Le Marois, G, Poitevin, Y, Salavy, J.F, Szczepanski, J

“…The main features of recent fusion reactor blanket conceptual designs using SiC f/SiC as structural material are presented. Particular attention is paid to the…”
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The EU advanced lead lithium blanket concept using SiC f/SiC flow channel inserts as electrical and thermal insulators by Norajitra, P., Bühler, L., Fischer, U., Kleefeldt, K., Malang, S., Reimann, G., Schnauder, H., Giancarli, L., Golfier, H., Poitevin, Y., Salavy, J.F.

“…Preparatory work on the EU advanced dual coolant (A-DC) blanket concept using SiC f/SiC flow channel inserts as electrical and thermal insulators has been…”
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The design of a new JET divertor for high triangularity and high current scenarios by Chappuis, P., Damiani, C., Guerin, C., Hurd, F., Loarte, A., Lomas, P., Lorenz, A., Paméla, J., Peacock, A., Portafaix, C., Rapp, J., Riccardo, V., Rimini, F., Saibene, G., Salavy, J.F., Sauce, Y., Sartori, R., Solano, E., Thomas, E., Thomas, P., Tsitrone, E., Valeta, M.P.

“…A new divertor (MKII-HP) has been designed to be implemented in JET as part of a possible enhancement programme of the JET facility (JET EP). The aim is to…”
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Manufacturing of a full scale baffle prototype for ITER with a CFC and W plasma spray armour by Merola, M, Bobin-Vastra, I, Cardella, A, Febvre, M, Giancarli, L, Plöchl, L, Salavy, J.F, Salito, A, Schedler, B, Vieider, G

“…The European contribution to the development of the ITER baffle will culminate with the fabrication of a full scale prototype with a CFC–plasma spray armour…”
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Performance of the TAURO blanket system associated with a liquid-metal cooled divertor by Golfier, H, Aiello, G, Fütterer, M.A, Gasse, A, Giancarli, L, Poitevin, Y, Salavy, J.F, Severi, Y, Szczepanski, J

“…Blankets and divertors are the key components of a fusion power plant due to their large impact on the overall plant design, performance and availability, and…”
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Potential and limits of water-cooled Pb–17Li blankets and divertors for a fusion power plant by Fütterer, M.A, Barleon, L, Giancarli, L, Puma, A.Li, Ogorodnikova, O.V, Poitevin, Y, Salavy, J.F, Szczepanski, J, Vella, G

“…Blankets and divertors are key components of a fusion power plant. They have a large impact on the overall plant design, its performance and availability, and…”
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