Results 21 to 30 of about 13,799 (192)

CFD Analysis and Optimization of the DEMO WCLL Central Outboard Segment Bottom-Cap Elementary Cell

open access: yesJournal of Nuclear Engineering, 2022
In the design of magnetic confinement nuclear fusion power plants, the breeding blanket (BB) plays a crucial role since it must fulfil key functions such as tritium breeding, radiation-shielding, and removal of the heat power generated by the plasma. The
Lorenzo Melchiorri   +4 more
doaj   +1 more source

Parametric thermal analysis for the optimization of Double Walled Tubes layout in the Water Cooled Lithium Lead inboard blanket of DEMO fusion reactor [PDF]

open access: yes, 2019
Within the roadmap that will lead to the nuclear fusion exploitation for electric energy generation, the construction of a DEMOnstration (DEMO) reactor is, probably, the most important milestone to be reached since it will demonstrate the technological ...
Arena P.   +4 more
core   +1 more source

Neutronics Assessment of the Spatial Distributions of the Nuclear Loads on the DEMO Divertor ITER-like Targets: Comparison between the WCLL and HCPB Blanket

open access: yesApplied Sciences, 2023
The Plasma Facing Components (PFCs) of the divertor target contribute to the fundamental functions of heat removal and particle exhaust during fusion operation, being subjected to a very hostile and complex loading environment characterized by intense ...
Simone Noce   +8 more
doaj   +1 more source

Statistical Analysis of Tritium Breeding Ratio Deviations in the DEMO Due to Nuclear Data Uncertainties

open access: yesApplied Sciences, 2021
For the stable and self-sufficient functioning of the DEMO fusion reactor, one of the most important parameters that must be demonstrated is the Tritium Breeding Ratio (TBR).
Jin Hun Park   +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 analysis of WCLL BB PbLi manifold

open access: yesFusion Engineering and Design, 2017
Abstract ENEA CR Brasimone has developed the new design of the Water Cooled Lithium Lead Breeding Blanket (WCLL BB). In the new design Breeding Zone (BZ) water coolant flows in radial-toroidal direction, and PbLi flows in radial-poloidal direction; a gap between the Back Plate (BP) and the BZ constitutes the PbLi inlet manifold.
MARTELLI, EMANUELA   +4 more
openaire   +2 more sources

MHD mixed convection flow in the WCLL: heat transfer analysis and cooling system [PDF]

open access: yes, 2019
In the Water-Cooled Lithium Lead (WCLL) blanket, a critical problem faced by the design is to ensure that the breeding zone (BZ) is properly cooled by the refrigeration system to keep the structural materials under the maximum allowed temperature by the ...
Caruso, Gianfranco   +3 more
core   +1 more source

3D MHD analysis of prototypical manifold for liquid metal blankets

open access: yesNuclear Fusion, 2023
The water-cooled lead lithium (WCLL) and the dual-cooled lead lithium (DCLL) are two of the breeding blanket (BB) concepts that the EUROfusion consortium is pursuing in the framework of the development of the fusion reactor industrial demonstrator DEMO ...
Simone Siriano   +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

Sizing of the Vacuum Vessel Pressure Suppression System of a Fusion Reactor Based on a Water‐Cooled Blanket, for the Purpose of the Preconceptual Design

open access: yesScience and Technology of Nuclear Installations, Volume 2016, Issue 1, 2016., 2016
A methodology to preliminarily evaluate the size of the suppression tank and the relief pipes for a Vacuum Vessel Pressure Suppression System, to be adopted in a fusion reactor based on a water cooled blanket, is presented. The volume of the ST depends on the total energy of the water cooling system and it can be sized based on a required final ...
Gianfranco Caruso   +2 more
wiley   +1 more source

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