Results 71 to 80 of about 1,034 (139)

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

Editorial : Special Issue on “Breeding Blanket: Design, Technology and Performance” [PDF]

, 2022
A prerequisite for establishing fusion power as one of the sources for low-carbon electricity generation is the demonstration of the capability of future fusion power plants in achieving tritium self-sufficiency and its capability of efficiently ...
Boccaccini, Lorenzo Virgilio, Ghidersa, Bradut-Eugen   +1 more
core   +2 more sources

A novel approach to the study of magnetohydrodynamic effect on tritium transport in WCLL breeding blanket of DEMO

Fusion Engineering and Design, 2021
Abstract The Water-Cooled Lithium Lead (WCLL) breeding blanket is one of the European blanket designs proposed for DEMO reactor. Tritium can permeate into the different structural materials, arising potential issues concerning the fuel self-sufficiency and can be lost into the environment with consequent radiological hazard for the population. Within
Candido, Luigi, Alberghi, Ciro, Moro, Fabio, Noce, Simone, Testoni, Raffaella, Utili, Marco, Zucchetti, Massimo   +6 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  

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

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

Magnetohydrodynamic simulation of the WCLL breeding blanket with helical cooling pipes

Fusion Engineering and Design
The Water-Cooled Lead Lithium (WCLL) is a Breeding Blanket (BB) concept presently in the development phase for implementation in the DEMO fusion reactor demonstrator. The Lead lithium eutectic alloy (PbLi) breeder is moved at a slow velocity to diminish Magnetohydrodynamics (MHD) pressure losses.
Alessandro Tassone, Simone Siriano
openaire   +1 more source

Helical-shaped double wall tubes solution for the breeding zone cooling in the WCLL breeding blanket

Fusion Engineering and Design
One of the two most promising Breeding Blanket (BB) concepts to be chosen as driver design of the EU-DEMO fusion reactor is the Water-Cooled Lead Lithium (WCLL) BB. A crucial point of this key component is the cooling of the BB structural elements and of the Lithium-Lead alloy, used as neutronic multiplier and Tritium breeder.
Maccari P., Arena P., Marinari R., Del Nevo A., Moro F., Noce S.   +5 more
openaire   +1 more source