Results 61 to 70 of about 502,482 (107)

Experimental and Numerical Results of LIFUS5/Mod3 Series E Test on In-Box LOCA Transient for WCLL-BB

open access: yesEnergies, 2021
The in-box LOCA (Loss of Coolant Accident) represents a major safety concern to be addressed in the design of the WCLL-BB (water-cooled lead-lithium breeding blanket).
Marica Eboli   +5 more
doaj   +1 more source

R&D Needs for the Design of the EU-DEMO HCPB ICD Balance of Plant in FP9

open access: yesJournal of Nuclear Engineering, 2022
During the Pre-Conceptual Design Phase of the EU-DEMO, two BOP solutions for WCLL and HCPB were elaborated, as close as possible to industrial standards.
Sara Perez-Martin   +3 more
doaj   +1 more source

SIMMER-III/ANSYS coupling (Preliminary development and validation activities of an integral tool for the design and analysis of WCLL components)

open access: yesMechanical Engineering Journal, 2023
In the framework of the development of fusion energy, one of the most prominent technologies arising to address the issues of tritium breeding and power conversion is the Water-Cooled Lithium-Lead (WCLL).
Nicolò BADODI   +3 more
doaj   +1 more source

Manufacturing of PAV-ONE, a Permeator against Vacuum Mock-Up with Niobium Membrane

open access: yesEnergies, 2023
The Permeator Against Vacuum (PAV) is one of the proposed technologies for the Tritium Extraction System of the WCLL BB (Water-Cooled Lithium-Lead Breeding Blanket) of the EU DEMO reactor.
Francesca Papa   +8 more
doaj   +1 more source

Modelling WCLL breeder blankets

open access: yes, 2021
International audienceThe key purpose of DEMO is to provide electricity from fusion power. An integral part to this design will be the tritium breeding blanket. Accurate modelling of hydrogen transport and inventories within the breeder blanket component
Grisolia, Christian   +6 more
core   +3 more sources

DEMO WCLL breeding zone cooling system design: Analysis and discussion [PDF]

open access: yes, 2019
The Water-Cooled Lithium-Lead (WCLL) Breeding Blanket (BB) is a key component in charge of ensuring Tritium self-sufficiency, shielding the Vacuum Vessel and removing the generated power of DEMO reactor.
Edemetti F.   +4 more
core   +2 more sources

Neutronic analyses in support of the WCLL DEMO design development

open access: yes, 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.   +13 more
core   +1 more source

Tritium transport model at breeder unit level for HCLL breeding blanket

open access: yesFusion 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   +3 more
openaire   +3 more sources

Tritium transport model at the minimal functional unit level for HCLL and WCLL breeding blankets of DEMO

open access: yesFusion Engineering and Design, 2018
Abstract The Helium-Cooled Lithium-Lead (HCLL) and Water-Cooled Lithium-Lead (WCLL) Breeding Blankets are two of the four European blanket designs proposed for the DEMO reactor. A tritium transport model inside the blanket is fundamental to assess its preliminary design and safety features. Tritium transport and permeation are complex phenomena to be
Candido, Luigi   +3 more
openaire   +1 more source

Numerical analysis of extreme magnetoconvective phenomena in the WCLL blanket

open access: yes, 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   +4 more
core  

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