Results 61 to 70 of about 410 (102)

Preliminary design of the top cap of DEMO Water-Cooled Lithium Lead breeding blanket segments [PDF]

open access: yes, 2020
Within the framework of EUROfusion R&D activity, a research campaign has been carried out at the University of Palermo, in close cooperation with ENEA labs, in order to preliminary design the top cap foreseen for the DEMO Water-Cooled Lithium Lead ...
Arena P.   +7 more
core   +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  

Modelling an in-vessel loss of coolant accident in the EU DEMO WCLL breeding blanket with the GETTHEM code

open access: yesFusion Engineering and Design, 2018
Abstract One of the accidents to be analyzed for the operation of the EU DEMO tokamak reactor is the in-vessel Loss-Of-Coolant Accident (LOCA), in which a postulated rupture in the First Wall causes a rapid pressurization of the Vacuum Vessel (VV).
Froio, Antonio   +5 more
openaire   +2 more sources

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

open access: yes, 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   +5 more
core   +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  

Neutronics Simulations for DEMO Diagnostics. [PDF]

open access: yesSensors (Basel), 2023
Luís R   +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

open access: yesNuclear 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   +4 more
doaj   +1 more source

Breeding blanket mock-up testing in IFMIF-DONES

open access: yesNuclear 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   +7 more
doaj   +1 more source

On the evaluation of the DEMO WCLL Breeding Blanket sector thermal-hydraulic performances at a system level

open access: yesFusion Engineering and Design
To obtain an affordable BB design, one of the key issues is assessing its thermal-hydraulic performances during operational and accidental conditions. For this, an analysis of the component transient behavior is needed to improve and refine the project.
Francesco Colliva   +5 more
openaire   +1 more source

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