Results 71 to 80 of about 506,130 (104)

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

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

Neutronic analyses in support of the WCLL DEMO design development

, 2018
In the frame of the EUROfusion Consortium programme, the Water Cooled Lithium Lead (WCLL) option has been chosen as a candidate for the breeding blanket (BB) of the European fusion power demonstration plant (DEMO) conceptual design.
Flammini D., Fabio Moro, Davide Flammini, Del Nevo A., Noce S., Moro F., Martelli E., Villari R., Simone Noce, Alessandro Del Nevo, Rosaria Villari, Mozzillo R., Emanuela Martelli, Rocco Mozzillo   +13 more
core   +1 more source

Thermal-hydraulic and thermo-mechanical simulations of Water-Heavy Liquid Metal interactions towards the DEMO WCLL breeding blanket design

Fusion engineering and design, 2019
The Water-Cooled Lithium Lead breeding blanket concept foresees the eutectic lithium-lead (Pb-15.7Li) alloy being cooled by pressurized sub-cooled water (temperature 295–328 °C; pressure 15.5 MPa) flowing in double wall tubes.
P. A. di Maio, P. Arena, F. D’Aleo, A. Del Nevo, M. Eboli, R. Forte, A. Pesetti   +6 more
semanticscholar   +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

Numerical analysis of extreme magnetoconvective phenomena in the WCLL blanket

, 2022
The Water-Cooled Lead-Lithium (WCLL) is one of the breeding blanket concepts currently being developed for implementation in the fusion reactor demonstrator DEMO. The liquid breeder, lead-lithium, is circulated at velocities lower than 1 mm/s to minimize
Gianfranco Caruso, Simone Siriano, Lorenzo Melchiorri, Alessandro Tassone, Pietro Arena   +4 more
core  

Optimization of the breeder zone cooling tubes of the DEMO Water-Cooled Lithium Lead breeding blanket

, 2016
The determination of an optimal configuration for the breeder zone (BZ) cooling tubes is one of the most important issues in the DEMO Water-Cooled Lithium Lead (WCLL) breeding blanket R&D activities, since BZ cooling tubes spatial distribution should ...
CHIOVARO, Pierluigi, Bongiovì, Gaetano, ARENA, Pietro, Del Nevo, A., DI MAIO, Pietro Alessandro, FORTE, Ruggero   +5 more
core   +1 more source

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

Implications of T loss in first wall armor and structural materials on T-self-sufficiency in future burning fusion devices

Nuclear Fusion
Future fusion reactors will have to breed enough tritium (T) to sustain continuous operation and to produce excess T to power up other fusion reactors. Therefore, T is a scarce resource that must not be lost inside the fusion power plants systems.
K. Schmid, T. Schwarz-Selinger, R. Arredondo, A. Theodorou, T. Pomella Lobo   +4 more
doaj   +1 more source

Breeding blanket mock-up testing in IFMIF-DONES

Nuclear Fusion
The fusion community is looking for solutions to qualify the breeding blankets (BB) before their final testing in DEMO. Thus, ambitious and attractive proposals, like the Volumetric Neutron Source, are being explored.
D. Rapisarda, P. Arena, F. Arranz, B. Brañas, F. Mota, M.I. Ortiz, A. Serikov, G. Zhou   +7 more
doaj   +1 more source