Results 51 to 60 of about 119 (88)

Development of anti-permeation and corrosion barrier coatings for the WCLL breeding blanket of the European DEMO

open access: yesFusion Engineering and Design, 2021
Abstract Tritium permeation from breeder material to the Water Coolant System (WCS) in Water Cooled Lithium Lead (WCLL) Breeding Blanket (BB) is one of the technological issues to be solved in the design of the European DEMO. Since the tritium extraction from the Water Coolant System is more challenging and expensive than the extraction from the ...
Marco Utili   +16 more
openaire   +3 more sources

Study of the EU-DEMO WCLL Breeding Blanket Primary Cooling Circuits Thermal-Hydraulic Performances during Transients Belonging to LOFA Category

open access: yesEnergies, 2021
The Breeding Blanket (BB) is one of the key components of the European Demonstration (EU-DEMO) fusion reactor. Its main subsystems, the Breeder Zone (BZ) and the First Wall (FW), are cooled by two independent cooling circuits, called Primary Heat ...
Cristiano Ciurluini   +3 more
doaj   +1 more source

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

European DEMO Fusion Reactor: Design and Integration of the Breeding Blanket Feeding Pipes

open access: yesEnergies, 2023
This article describes the design and configuration of the DEMO Breeding Blanket (BB) feeding pipes inside the upper port. As large BB segments require periodic replacement via the upper vertical ports, the space inside the upper port needs to be ...
Rocco Mozzillo   +4 more
doaj   +1 more source

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

Water-cooled lead and ceramic breeder (WLCB) breeding blanket (BB) for the EU DEMO: Neutronic campaigns for T breeding optimization

open access: yesNuclear Materials and Energy
A novel Breeding Blanket (BB) concept, the Water-cooled Lead and Ceramic Breeder (WLCB) BB, has been developed under the EUROfusion Programme to address key challenges identified during the Pre-Conceptwual Design (PCD) phase for the driver BB concepts ...
Iole Palermo   +6 more
doaj   +1 more source

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

Main Nuclear Responses of the DEMO Tokamak with Different In-Vessel Component Configurations

open access: yesApplied Sciences
Research and development of the DEMOnstration power plant (DEMO) breeder blanket (BB) has been performed in recent years based on a predefined DEMO tritium breeding ratio (TBR) requirement, which determines a loss of wall surface due to non-breeding in ...
Jin Hun Park, Pavel Pereslavtsev
doaj   +1 more source

Home - About - Disclaimer - Privacy