Search Results - "Nevo, A. Del"

Modelling of thermal conductivity and melting behaviour of minor actinide-MOX fuels and assessment against experimental and molecular dynamics data by Magni, A., Luzzi, L., Pizzocri, D., Schubert, A., Van Uffelen, P., Nevo, A. Del

“…•Modelling of thermal conductivity and melting temperature of minor actinide-MOX fuels.•Review of state-of-the-art data and correlations available in…”
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Status of maturation of critical technologies and systems design: Breeding blanket by Boccaccini, L.V., Arbeiter, F., Arena, P., Aubert, J., Bühler, L., Cristescu, I., Nevo, A. Del, Eboli, M., Forest, L., Harrington, C., Hernandez, F., Knitter, R., Neuberger, H., Rapisarda, D., Sardain, P., Spagnuolo, G.A., Utili, M., Vala, L., Venturini, A., Vladimirov, P., Zhou, Guangming

“…The scope of the EUFOfusion Work Package Breeding Blanket is to develop a blanket concept for the EU DEMO reactor; this includes the blanket segments inside…”
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Preliminary Thermo-Mechanical Design of the Once Through Steam Generator and Molten Salt Intermediate Heat Exchanger for EU DEMO by Zaupa, M., Palma, M. Dalla, Nevo, A. Del, Moscato, I., Tarallo, A., Barucca, L.

“…The European DEMOnstration power plant (DEMO) is considered to be the nearest-term fusion reactor capable of producing several hundred MWs of net electricity,…”
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Status of Pb-16Li technologies for European DEMO fusion reactor by Utili, M., Bassini, S., Boccaccini, L., Bühler, L., Cismondi, F., Del Nevo, A., Eboli, M., DiFonzo, F., Hernandez, T., Wulf, S., Kordač, M., Martelli, D., De les Valls, E. Mas, Melichar, T., Mistrangelo, C., Tarantino, M., Tincani, A., Vála, L.

“…•The preliminary Pb15.7Li Loop layout was shown in the paper.•The Magneto Hydro Dynamic effect induced in the flowing Pb-16Li inside BB and the pressure drops…”
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Thermal-hydraulic and thermo-mechanical simulations of Water-Heavy Liquid Metal interactions towards the DEMO WCLL breeding blanket design by Di Maio, P.A., Arena, P., D’Aleo, F., Del Nevo, A., Eboli, M., Forte, R., Pesetti, A.

“…The Water-Cooled Lithium Lead breeding blanket concept foresees the eutectic lithium-lead (Pb-15.7Li) alloy being cooled by pressurized sub-cooled water…”
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Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment by Luzzi, L., Barani, T., Boer, B., Cognini, L., Del Nevo, A., Lainet, M., Lemehov, S., Magni, A., Marelle, V., Michel, B., Pizzocri, D., Schubert, A., Van Uffelen, P., Bertolus, M.

“…The design phase and safety assessment of Generation IV liquid metal-cooled fast reactors calls for the improvement of fuel pin performance codes, in…”
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Lithium-Lead/water interaction: LIFUS5/Mod3 series E tests analysed by SIMMER-III coupled with RELAP5 by Cossu, V., Galleni, F., Eboli, M., Nevo, A. Del, Forgione, N., Paci, S.

“…The Breeding Blanket is a necessary component to close the nuclear fusion reactor fuel cycle. amongst the most promising conceptual design, there is the Water…”
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Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project by Del Nevo, A., Arena, P., Caruso, G., Chiovaro, P., Di Maio, P.A., Eboli, M., Edemetti, F., Forgione, N., Forte, R., Froio, A., Giannetti, F., Di Gironimo, G., Jiang, K., Liu, S., Moro, F., Mozzillo, R., Savoldi, L., Tarallo, A., Tarantino, M., Tassone, A., Utili, M., Villari, R., Zanino, R., Martelli, E.

“…The water-cooled lithium-lead breeding blanket is in the pre-conceptual design phase. It is a candidate option for European DEMO nuclear fusion reactor. This…”
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Experimental investigation and SIMMER-III code modelling of LBE–water interaction in LIFUS5/Mod2 facility by Pesetti, A., Del Nevo, A., Forgione, N.

“…•In the framework of THINS Project, four experimental tests were performed investigating water–LBE interaction in LIFUS5/Mod2 facility at ENEA RC…”
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Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment by Luzzi, L, Barani, T, Boer, B, Cognini, L, Nevo, A. Del, Lainet, M, Lemehov, S, Magni, A, Marelle, V, Michel, B, Pizzocri, D, Schubert, A, Uffelen, P. Van, Bertolus, M

“…The design phase and safety assessment of Generation IV liquid metal-cooled fast reactors calls for the improvement of fuel pin performance codes, in…”
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Pre-conceptual design of EU DEMO balance of plant systems: Objectives and challenges by Barucca, L., Bubelis, E., Ciattaglia, S., D’Alessandro, A., Del Nevo, A., Giannetti, F., Hering, W., Lorusso, P., Martelli, E., Moscato, I., Quartararo, A., Tarallo, A., Vallone, E.

“…The European Research Roadmap to the Realisation of Fusion Energy foresees that the DEMO reactor is going to succeed ITER in the pathway towards the…”
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Advancements in DEMO WCLL breeding blanket design and integration by Martelli, E., Del Nevo, A., Arena, P., Bongiovì, G., Caruso, G., Di Maio, P. A., Eboli, M., Mariano, G., Marinari, R., Moro, F., Mozzillo, R., Giannetti, F., Di Gironimo, G., Tarallo, A., Tassone, A., Villari, R.

“…Summary The water‐cooled lithium–lead breeding blanket is a candidate option for the European Demonstration Power Plant (DEMO) nuclear fusion reactor. This…”
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Post-test simulation of a PLOFA transient test in the CIRCE-HERO facility by Narcisi, V., Giannetti, F., Del Nevo, A., Tarantino, M., Caruso, G.

“…•CIRCE-HERO protected loss of flow accident analysis and comparison with experimental data.•Thermal hydraulics benchmark activity performed within the EU H2020…”
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Design and preliminary analyses of the new Water Cooled Lithium Lead TBM for ITER by Aubert, J., Aiello, G., Alonso, D., Batal, T., Boullon, R., Burles, S., Cantone, B., Cismondi, F., Del Nevo, A., Maqueda, L., Morin, A., Rodríguez, E., Rueda, F., Soldaini, M., Vallory, J.

“…In the European strategy, DEMO is the intermediate step between ITER and a commercial fusion power plant. In this framework, one of the goal of DEMO is to be a…”
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Preliminary design of a helical coil steam generator mock-up for the CIRCE facility for the development of DEMO LiPb heat exchanger by Tarantino, M., Lorusso, P., Del Nevo, A., Di Piazza, I., Giannetti, F., Martelli, D.

“…In the framework of the EU DEMO fusion reactor technology development, a new steam generator consisting in a helical tube bundle is currently under study for…”
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Investigation of heat transfer in a steam generator bayonet tube for the development of PbLi technology for EU DEMO fusion reactor by Martelli, E., Del Nevo, A., Lorusso, P., Giannetti, F., Narcisi, V., Tarantino, M.

“…•Experimental campaign on HERO test section is presented to demonstrate technological feasibility of a steam generator bayonet tube.•Steam generator bayonet…”
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WCLL breeding blanket design and integration for DEMO 2015: status and perspectives by Del Nevo, A., Martelli, E., Agostini, P., Arena, P., Bongiovì, G., Caruso, G., Di Gironimo, G., Di Maio, P.A., Eboli, M., Giammusso, R., Giannetti, F., Giovinazzi, A., Mariano, G., Moro, F., Mozzillo, R., Tassone, A., Rozzia, D., Tarallo, A., Tarantino, M., Utili, M., Villari, R.

“…Water-cooled lithium-lead breeding blanket is considered a candidate option for European DEMO nuclear fusion reactor. ENEA and the linked third parties have…”
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Preliminary analysis of an in-box LOCA in the breeding unit of the WCLL TBM for the ITER reactor with SIMMER-IV code by Galleni, F., Moscardini, M., Eboli, M., Del Nevo, A., Martelli, D., Forgione, N.

“…The in-box LOCA (Loss of Coolant Accident) represents a major safety concern to be addressed in the design of the WCLL-BB (Water-Cooled Lead-Lithium Breeding…”
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Corrigendum to “MHD forced convection flow in dielectric and electro-conductive rectangular annuli” [Fusion Eng. Des. 159 (2020) 111773] by Siriano, S., Tassone, A., Caruso, G., Del Nevo, A.

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Corrigendum to “Electromagnetic coupling phenomena in co-axial rectangular channels“ [Fusion Engineering and Design 160 (2020), 111854] by Siriano, S., Tassone, A., Caruso, G., Del Nevo, A.

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