Results 51 to 60 of about 13,835 (203)

Water-cooled lead and ceramic breeder (WLCB) breeding blanket (BB) for the EU DEMO: Neutronic campaigns for T breeding optimization

Nuclear Materials and Energy
A novel Breeding Blanket (BB) concept, the Water-cooled Lead and Ceramic Breeder (WLCB) BB, has been developed under the EUROfusion Programme to address key challenges identified during the Pre-Conceptwual Design (PCD) phase for the driver BB concepts ...
Iole Palermo, Francisco A. Hernandez, Salvatore D’Amico, Jin Hun Park, Pavel Pereslavtsev, Guangming Zhou, Iñaki Zumalde   +6 more
doaj   +1 more source

Investigation of the DEMO WCLL Breeding Blanket Cooling Water Activation

Fusion Engineering and Design, 2019
Abstract Within the framework of the activities foreseen by the EUROfusion action on the cooling water activation assessment for a DEMO reactor equipped with a Water Cooled Lithium Lead Breeding Blanket (WCLL BB), the University of Palermo is involved in the assessment of dose rates induced by the decay of nitrogen radioisotopes produced by water ...
Chiovaro, P., Ciattaglia, S., Cismondi, F., Del Nevo, A., Maio, P. A. Di, Federici, G., Frittitta, C., Moscato, I., Vallone, E.   +8 more
openaire   +5 more sources

An optimized BSCCO/Ag resonator coil for utility use [PDF]

, 2000
AC coils made with BSCCO-2223/Ag tapes and operating in liquid nitrogen have a potential for power related applications, e.g., inductors, transformers and current limiters.
Broeren, B., Damstra, G.C., Godeke, A., Haken, B. ten, Kate, H.H.J. ten, Klein Schiphorst, P., Krooshoop, H.J.G., Rutten, G., Scholten, A., Shevchenko, O.A., Spoorenberg, C.J.G.   +10 more
core   +2 more sources

3D Transient CFD Simulation of an In-Vessel Loss-of-Coolant Accident in the EU DEMO WCLL Breeding Blanket

Energies, 2023
The in-vessel Loss-of-Coolant Accident (LOCA) is one of the design basis accidents in the design of the EU DEMO tokamak fusion reactor. System-level codes are typically employed to analyse the evolution of these transients.
Mauro Sprò, Antonio Froio, Andrea Zappatore   +2 more
doaj   +1 more source

Verification and Validation of COMSOL Magnetohydrodynamic Models for Liquid Metal Breeding Blankets Technologies

Energies, 2021
Liquid metal breeding blankets are extensively studied in nuclear fusion. In the main proposed systems, the Water Cooled Lithium Lead (WCLL) and the Dual Coolant Lithium Lead (DCLL), the liquid metal flows under an intense transverse magnetic field, for ...
Ciro Alberghi, Luigi Candido, Raffaella Testoni, Marco Utili, Massimo Zucchetti   +4 more
doaj   +1 more source

WCLL breeding blanket design and integration for DEMO 2015: status and perspectives

Fusion Engineering and Design, 2017
Abstract Water-cooled lithium-lead breeding blanket is considered a candidate option for European DEMO nuclear fusion reactor. ENEA and the linked third parties have proposed and are developing a multi-module blanket segment concept based on DEMO 2015 specifications. The layout of the module is based on horizontal (i.e. radial-toroidal) water-cooling
Del Nevo, A., MARTELLI, EMANUELA, Agostini, P., Arena, P., Bongiovì, G., CARUSO, Gianfranco, Di Gironimo, G., Di Maio, P. A., Eboli, M., Giammusso, R., GIANNETTI, FABIO, Giovinazzi, A., Mariano, G., Moro, F., Mozzillo, R., TASSONE, ALESSANDRO, Rozzia, D., Tarallo, A., Tarantino, M., Utili, M., Villari, R.   +20 more
openaire   +3 more sources

Tritium Extraction from Lithium–Lead Eutectic Alloy: Experimental Characterization of a Permeator against Vacuum Mock-Up at 450 °C

Energies, 2023
Tritium extraction is one of the key open issues toward the development of the WCLL BB (Water-Cooled Lithium–Lead Breeding Blanket) of EU DEMO reactors, and different technologies have been proposed to address it. Among them, the Permeator Against Vacuum
Francesca Papa, Alessandro Venturini, Daniele Martelli, Marco Utili   +3 more
doaj   +1 more source

Special Libraries, January 1925 [PDF]

, 1923
Volume 16, Issue 1https://scholarworks.sjsu.edu/sla_sl_1925/1000/thumbnail ...
Special Libraries Association
core   +3 more sources

Preliminary assessment of tritium permeation and retention in the European Water Cooled Lithium Lead Test Blanket Module with TESSIM-X

Nuclear Materials and Energy, 2022
Tritium self-sufficiency is a key requirement for future fusion power plants. Therefore, it will be necessary to minimize tritium losses to the surrounding systems, such as the tritium breeding modules, plasma-facing components, cooling system, etc ...
R. Arredondo, K. Schmid, I. Ricapito, A. Lukenskas, G.A. Spagnuolo   +4 more
doaj   +1 more source

Digital memory sense amplifying means Patent [PDF]

, 1968
Digital magnetic core memory with sensing amplifier ...
Milligan, G. C.
core   +1 more source