Results 51 to 60 of about 1,034 (139)

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

Recent Progress in the WCLL Breeding Blanket Design for the DEMO Fusion Reactor

open access: yesIEEE Transactions on Plasma Science, 2018
The water-cooled lithium-lead (PbLi) breeding blanket is one of the candidate systems considered for the implementation in the European Demonstration Power Plant (DEMO) nuclear fusion reactor. This concept employs PbLi liquid metal as tritium breeder and neutron multiplier, water pressurized at 15.5 MPa as the coolant, and EUROFER as the structural ...
Alessandro Tassone   +16 more
openaire   +4 more sources

Tritium Extraction from Lithium–Lead Eutectic Alloy: Experimental Characterization of a Permeator against Vacuum Mock-Up at 450 °C

open access: yesEnergies, 2023
Tritium extraction is one of the key open issues toward the development of the WCLL BB (Water-Cooled Lithium–Lead Breeding Blanket) of EU DEMO reactors, and different technologies have been proposed to address it. Among them, the Permeator Against Vacuum
Francesca Papa   +3 more
doaj   +1 more source

Analysis of EM loads on DEMO WCLL breeding blanket during VDE-up

open access: yesFusion Engineering and Design, 2018
Abstract This work presents the development of a DEMO EM model based on the WCLL design able to evaluate EM loads during normal and off-normal operations. The model has the capability to use periodic boundary conditions (in order to analyze EM transients in presence of both toroidal and poloidal field) and elements supporting non-linear magnetic ...
Ivan A. Maione   +6 more
openaire   +5 more sources

CFD simulation of the magnetohydrodynamic flow inside the WCLL breeding blanket module

open access: yesFusion Engineering and Design, 2017
Abstract The interaction between the molten metal and the plasma-containing magnetic field in the breeding blanket causes the onset of a magnetohydrodynamic (MHD) flow. To properly design the blanket, it is important to quantify how and how much the flow features are modified compared with an ordinary hydrodynamic flow.
TASSONE, ALESSANDRO   +3 more
openaire   +2 more sources

Long-term corrosion behavior of ODS-Eurofer in flowing Pb-15.7Li at 550°C

open access: yesNuclear Materials and Energy, 2016
Low activation ferritic-martensitic steels (RAFM-steels) are foreseen as structural materials in different blanket designs (HCLL, DCLL, WCLL) with Pb-15.7Li as breeding and partly also as cooling medium.
W. Krauss, S.-E. Wulf, J. Konys
doaj   +1 more source

STEAM Experimental Facility: A Step Forward for the Development of the EU DEMO BoP Water Coolant Technology

open access: yesEnergies, 2023
Within the EUROfusion roadmap for the technological development of the European-DEMOnstration (EU-DEMO) reactor, a key point has been identified in the discontinuous operation (pulse-dwell-pulse) of the machine.
Alessandra Vannoni   +14 more
doaj   +1 more source

Status, Features, and Future Development of the LIFUS5/Mod4 Experimental Facility Design

open access: yesApplied Sciences, 2022
The Water-Cooled Lithium–Lead (WCLL) is one of the most promising technologies for power conversion and tritium production in future fusion-powered reactors; it will be implemented in one of the Test Breeding Modules (TBM) inside the ITER reactor and the
Nicolò Badodi   +3 more
doaj   +1 more source

Status of maturation of critical technologies and systems design: Breeding blanket [PDF]

open access: yes, 2022
The scope of the EUFOfusion Work Package Breeding Blanket is to develop a blanket concept for the EU DEMO reactor; this includes the blanket segments inside the Vacuum Vessel and the related Tritium Extraction/Removal Systems.
Arbeiter, F.   +20 more
core   +2 more sources

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