Results 51 to 60 of about 1,037 (124)
Structural assessment of the EU-DEMO WCLL Central Outboard Blanket segment under normal and off-normal operating conditions [PDF]
Within the framework of the EUROfusion design activities concerning the EU-DEMO Breeding Blanket (BB) system, a research campaign has been carried out at the University of Palermo with the aim of investigating the structural behaviour of the DEMO Water ...
Arena P. +9 more
core +1 more source
Experimental and Numerical Results of LIFUS5/Mod3 Series E Test on In-Box LOCA Transient for WCLL-BB
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
Numerical study of laminar magneto-convection in a differentially heated square duct [PDF]
Magnetohydrodynamic pressure drops are one of the main issues for liquid metal blanket in fusion reactors. Minimize the fluid velocity at few millimeters per second is one strategy that can be employed to address the problem.
Caruso, Gianfranco +2 more
core +1 more source
The in-vessel Loss-of-Coolant Accident (LOCA) is one of the design basis accidents in the design of the EU DEMO tokamak fusion reactor. System-level codes are typically employed to analyse the evolution of these transients.
Mauro Sprò +2 more
doaj +1 more source
R&D Needs for the Design of the EU-DEMO HCPB ICD Balance of Plant in FP9
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
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
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
Multiphysics Optimization for First Wall Design Enhancement in Water-Cooled Breeding Blankets [PDF]
The commercial feasibility of the first fusion power plant generation adopting D-T plasma is strongly dependent upon the self-sustainability in terms of tritium fuelling. Within such a kind of reactor, the component selected to house the tritium breeding
Chiovaro P. +3 more
core +1 more source
Recent Progress in the WCLL Breeding Blanket Design for the DEMO Fusion Reactor
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 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

