Results 71 to 80 of about 1,037 (124)

Status of maturation of critical technologies and systems design: Breeding blanket [PDF]

, 2022
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 the Vacuum Vessel and the related Tritium Extraction/Removal Systems.
Arbeiter, F., Arena, P., Aubert, J., Boccaccini, L. V., Bühler, L., Cristescu, I., Eboli, M., Forest, L., Harrington, C., Hernandez, F., Knitter, R., Neuberger, H., Nevo, A. Del, Rapisarda, D., Sardain, P., Spagnuolo, G. A., Utili, M., Vala, L., Venturini, A., Vladimirov, P., Zhou, Guangming   +20 more
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Preliminary thermo-mechanical assessment of the Top Cap region of the Water-Cooled Lead-Ceramic Breeder Breeding Blanket alternative concept [PDF]

The Water-Cooled Lead Lithium (WCLL) and the Helium-Cooled Pebble Bed (HCPB) Breeding Blanket (BB) concepts are the two candidates currently poised to be chosen as the driver blanket for the EU DEMO reactor.
Arena, P., Bongiovì, G., Catanzaro, I., Chiovaro, P., Giambrone, S., Giardina, M., Hernández, F. A., Maio, P. A. Di, Moscato, I., Quartararo, A., Spagnuolo, G. A., Tomarchio, E., Vallone, E.   +12 more
core   +6 more sources

Activation and decay heat analysis of the European DEMO blanket concepts [PDF]

, 2017
Demonstrating tritium self-sufficiency is an important goal of the European tokamak demonstration fusion reactor. Currently four breeder blanket concepts are being considered: the Helium Cooled Pebble Bed (HCPB), Helium Cooled Lithium-Lead (HCLL), Dual ...
Eade, T., Garcia, M., Garcia, R., Ogando, F., Pereslavtsev, P., Sanz, J., Stankunas, G., Travleev, Anton   +7 more
core   +2 more sources

A complete EM analysis of DEMO WCLL Breeding Blanket segments during VDE-up

Fusion Engineering and Design, 2019
Abstract Considerable effort is made within the EUROfusion consortium to analyse the electromagnetic (EM) loads that act on the in-vessel components of DEMO during normal and off-normal operations. These loads are important, often design driving, inputs for the structural assessment of such components. With regard to the Breeding Blanket (BB) project,
Maione, Ivan Alessio, Roccella, Massimo, Marin, Anna, Bertolini, Claudio, Lucca, Flavio   +4 more
openaire   +4 more sources

Main Nuclear Responses of the DEMO Tokamak with Different In-Vessel Component Configurations

Applied Sciences
Research and development of the DEMOnstration power plant (DEMO) breeder blanket (BB) has been performed in recent years based on a predefined DEMO tritium breeding ratio (TBR) requirement, which determines a loss of wall surface due to non-breeding in ...
Jin Hun Park, Pavel Pereslavtsev
doaj   +1 more source

Dose rate evaluation in the technical premises of the demo fusion reactor using the serpent Monte Carlo code [PDF]

Nuclear Technology and Radiation Protection
This paper presents a dose rate assessment within the DEMO fusion reactor's auxiliary premises, focusing on activated water and Activated Corrosion Products as primary radiation sources.
Sereda Svitlana, Sereda Serhii, Ciattaglia Sergio, Nosovsky Anatoly, Gulik Volodymyr   +4 more
doaj   +1 more source

Tritium transport model at breeder unit level for HCLL breeding blanket

Fusion Engineering and Design, 2019
Abstract The Helium-Cooled Lithium Lead (HCLL) breeding blanket is one of the European blanket designs proposed for DEMO reactor. A tritium transport model is fundamental for the correct assessment of both design and safety, in order to guarantee tritium self-sufficiency and to characterize tritium concentrations, inventories and losses.
Raffaella Testoni, Luigi Candido, Marco Utili, Massimo Zucchetti   +3 more
openaire   +3 more sources

Hybrid 1D + 2D Modelling for the Assessment of the Heat Transfer in the EU DEMO Water-Cooled Lithium-Lead Manifolds

Energies, 2020
The European demonstration fusion power reactor (EU DEMO) tokamak will be the first European fusion device to produce electricity and to include a breeding blanket (BB).
Antonio Froio, Andrea Bertinetti, Alessandro Del Nevo, Laura Savoldi   +3 more
doaj   +1 more source

Thermal-hydraulic assessment of Once-Through Steam Generators for EU-DEMO WCLL Breeding Blanket primary cooling system application

Fusion Engineering and Design, 2023
Once-Through Steam Generators (OTSGs) were recently selected to be installed in the Primary Heat Transfer Systems (PHTS) related to EU-DEMO WCLL Breeding Blanket (BB). Referring to the Balance of Plant Direct Coupling Design (BoP-DCD) option, these components are used to deliver the thermal power removed from the two principal blanket subsystems, i.e ...
C. Ciurluini, Alessandra Vannoni, Tommaso Del Moro, Pierdomenico Lorusso, Amelia Tincani, Alessandro Del Nevo, Luciana Barucca, Fabio Giannetti   +7 more
openaire   +1 more source

Thermal-hydraulic study and optimization of the DEMO Water Cooled Lithium-Lead Breeding Blanket [PDF]

, 2021
One of the key components of a nuclear fusion power plant is the Breeding Blanket (BB), in charge of ensuring the essential functions of Tritium production, shield the Vacuum Vessel (VV) and remove the heat generated in the toroidal chamber.
EDEMETTI, FRANCESCO
core