Results 51 to 60 of about 933 (168)

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

Activities in Divertor Reflector and Linear Plates Using WCLL and HCPB Breeding Blanket Concepts

Energies, 2021
In fusion devices, such as European Demonstration Fusion Power Reactor (EU DEMO), primary neutrons can cause material activation due to the interaction between the source particles and the targeting material.
Simona Breidokaite, Gediminas Stankunas
doaj   +1 more source

Thermofluid-dynamic and thermal–structural assessment of the EU-DEMO WCLL “double bundle” Breeding Blanket concept left outboard segment [PDF]

As part of the activities performed by the DEMO Central Team (DCT) to study alternative configurations of the Water-Cooled Lead Lithium (WCLL) Breeding Blanket (BB), to overcome the open issues that emerged at the end of the Pre-Conceptual Design phase ...
Moscato, I., Giambrone, S., Spagnuolo, G. A., Hernández, F. A., Bongiovì, G., Chiovaro, P., Gioè, A., Quartararo, A., Vallone, E., Maio, P. A. Di, Catanzaro, I., Castrovinci, F. M.   +11 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

Activity and decay heat calculations for the European DEMO WCLL breeder blanket module including activated LiPb flow

, 2019
This paper presents the analyses performed within the SAE (Safety and Environment) project of EUROfusion/PPPT aimed at providing up-to-date estimates of the activity inventories and the decay heat generation in the WCLL.
Stankunas G., Moro F., Tidikas A.
core   +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

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

Thermo-hydraulic analysis of EU DEMO WCLL breeding blanket

Fusion Engineering and Design, 2018
Abstract In the frame of EUROfusion Work Package Breeding Blanket, thermal-hydraulic engineering analyses were carried out at ENEA Brasimone, in close cooperation with Sapienza University of Rome, to investigate thermal and fluid-dynamic behavior of the Water Cooled Lithium Lead Breeding Blanket, which is a candidate option for the European DEMO ...
Martelli, Emanuela, Caruso, Gianfranco, Giannetti, Fabio, Del Nevo, Alessandro   +3 more
openaire   +1 more source

W-HYDRA: a new experimental platform for the Water-Cooled Lead Lithium Breeding Blanket

Nuclear Fusion
In the framework of the activities coordinated by the EUROfusion consortium, the Water thermal-HYDRAulic (W-HYDRA) experimental platform is being built at the ENEA Brasimone Research Centre in order to support the development of the Water-Cooled Lead ...
P. Arena, A. Del Nevo, M. Eboli, B. Gonfiotti, P. Maccari, R. Marinari, A. Tincani, N. Badodi, G. Bongiovì, I. Catanzaro, F. Galleni, C. Risi, L.L. Sanasi, A. Tarallo, A. Vannoni   +14 more
doaj   +1 more source

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