Results 51 to 60 of about 513 (179)

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

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

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

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

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

High heat flux limits of the fusion reactor water-cooled first wall

Nuclear Engineering and Technology, 2019
The water-cooled WCLL blanket is one of the possible candidates for the blanket of the fusion power reactors. The plasma-facing first wall manufactured from the reduced-activation ferritic-martensitic steel Eurofer97 will be cooled with water at a ...
Pavel Zacha, Slavomir Entler
doaj   +1 more source

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

Recent Progress in the WCLL Breeding Blanket Design for the DEMO Fusion Reactor

IEEE Transactions on Plasma Science, 2018
The water-cooled lithium-lead (PbLi) breeding blanket is one of the candidate systems considered for the implementation in the European Demonstration Power Plant (DEMO) nuclear fusion reactor. This concept employs PbLi liquid metal as tritium breeder and neutron multiplier, water pressurized at 15.5 MPa as the coolant, and EUROFER as the structural ...
Alessandro Tassone, Alessandro Del Nevo, Pietro Arena, Gaetano Bongiovi, Gianfranco Caruso, Pietro Alessandro di Maio, Giuseppe di Gironimo, Marica Eboli, Nicola Forgione, Ruggero Forte, Fabio Giannetti, Giovanni Mariano, Emanuela Martelli, Fabio Moro, Rocco Mozzillo, Andrea Tarallo, Rosaria Villari   +16 more
openaire   +4 more sources

Neutronics Simulations for DEMO Diagnostics. [PDF]

Sensors (Basel), 2023
Luís R, Nietiadi Y, Quercia A, Vale A, Belo J, Silva A, Gonçalves B, Malaquias A, Gusarov A, Caruggi F, Perelli Cippo E, Chernyshova M, Bienkowska B, Biel W.   +13 more
europepmc   +1 more source