Results 11 to 20 of about 933 (168)

Integration of LiPb loops for WCLL BB of European DEMO

Fusion Engineering and Design, 2021
The eutectic alloy Lithium Lead (LiPb) enriched at 90 % in 6Li is the breeder material for one of the candidate European Breeding Blanket (BB) concepts.
Tincani A., Mozzillo R., Gliss C., Utili M., Venturini A.   +4 more
core   +4 more sources

CFD Analysis and Optimization of the DEMO WCLL Central Outboard Segment Bottom-Cap Elementary Cell [PDF]

Journal of Nuclear Engineering, 2022
In the design of magnetic confinement nuclear fusion power plants, the breeding blanket (BB) plays a crucial role since it must fulfil key functions such as tritium breeding, radiation-shielding, and removal of the heat power generated by the plasma. The
Lorenzo Melchiorri, Pietro Arena, Fabio Giannetti, Simone Siriano, Alessandro Tassone   +4 more
doaj   +2 more sources

Conceptual Design of the Steam Generators for the EU DEMO WCLL Reactor

Energies, 2023
In the framework of the EUROfusion Horizon Europe Programme, ENEA and its linked third parties are in charge of the conceptual design of the steam generators belonging to EU DEMO WCLL Breeding Blanket Primary Heat Transfer Systems (BB PHTSs).
Amelia Tincani, Cristiano Ciurluini, Alessandro Del Nevo, Fabio Giannetti, Andrea Tarallo, Claudio Tripodo, Antonio Cammi, Alessandra Vannoni, Marica Eboli, Tommaso Del Moro, Pierdomenico Lorusso, Luciana Barucca   +11 more
doaj   +3 more sources

Rationale and Method for design of DEMO WCLL Breeding Blanket Poloidal Segmentation

Fusion Engineering and Design, 2017
One of the most critical components in the design of DEMO Power Plant is the Breeding Blanket (BB). Currently, four candidates are investigated as options for DEMO. One of these is the Water Coolant Lithium Lead (WCLL) Breeding Blanket (BB).
Rocco Mozzillo, P.h. D., Aleessandro Del Nevo , Ph D, Giuseppe Di Gironimo, PhD, MARTELLI, EMANUELA   +3 more
core   +5 more sources

Tritium permeation modelling in DEMO WCLL cooling system

Fusion Engineering and Design, 2020
Tritium management is one of the most critical aspects in DEMO design. Knowledge of tritium permeation is a priority both in terms of safety and plant performance, as it may represent a radiological risk for the employed personnel and a significance loss
Santucci, Alessia, Tosti, Silvano, Noschese, Leonardo, Romanelli, Francesco   +3 more
core   +4 more sources

Design of a Test Section for the Experimental Investigation of the WCLL Manifold Hydraulic Features

Energies, 2023
A scaled-down test section representative of an Outboard Segment manifold of the Water-Cooled Lithium Lead Breeding Blanket for the European DEMO has been designed for installation and test in a high- mass flow branch of the W-HYDRA facility, under ...
Aldo Collaku, Pietro Arena, Alessandro Del Nevo, Ranieri Marinari, Laura Savoldi   +4 more
doaj   +2 more sources

Overview of tritium management in WCLL test blanket system of ITER

Fusion Engineering and Design
A key aspect for the achievement of the fuel self-sufficiency of future fusion power plants is the management of tritium in the different stages of the reactor fuel cycle.
Ricapito I., Candido L., Aiello A., Moreno C., Ortiz-Ferrer C., La Rovere S.   +5 more
core   +2 more sources

Maintenance study on WCLL-TBS ancillary systems in process room

Fusion Engineering and Design
The Water-Cooled Lithium Lead Test Blanket System (WCLL-TBS) is one of the European TBS candidates for being installed and operated in ITER. The ongoing activities toward the Preliminary Design Review of the WCLL-TBS Ancillary Systems include the ...
Marzullo, Domenico, Bonavolontà, Ugo, La Rovere, Stefano, Ferrer, Carlos Ortiz   +3 more
core   +3 more sources

Analysis of the Thermo-Mechanical Behaviour of the EU DEMO Water-Cooled Lithium Lead Central Outboard Blanket Segment under an Optimized Thermal Field

Applied Sciences, 2022
Within the framework of the EUROfusion research activities on the DEMO Water-Cooled Lithium Lead (WCLL) Breeding Blanket (BB) design, a research study was performed to preliminarily optimize, from the thermal point of view, the WCLL Central Outboard ...
Ilenia Catanzaro, Gaetano Bongiovì, Pietro Alessandro Di Maio   +2 more
doaj   +1 more source

Advancements in DEMO WCLL breeding blanket design and integration

International Journal of Energy Research, 2018
The water-cooled lithium–lead breeding blanket is a candidate option for the European Demonstration Power Plant(DEMO) nuclear fusion reactor. This breeding blanket concept relies on the liquid lithium– lead as breeder–multiplier,pressurized water as coolant, and EUROFER as structural material.
Martelli, E., Del Nevo, A., Arena, P., Bongiovì, G., Caruso, G., Di Maio, P. A. ., Eboli, M., Mariano, G., Marinari, R., Moro, F., MOZZILLO, ROCCO, Giannetti, F., DI GIRONIMO, GIUSEPPE, TARALLO, ANDREA, Tassone, A., Villari, S.   +16 more
  +9 more sources