Results 41 to 50 of about 410 (102)

Preliminary assessment of tritium permeation and retention in the European Water Cooled Lithium Lead Test Blanket Module with TESSIM-X

Nuclear Materials and Energy, 2022
Tritium self-sufficiency is a key requirement for future fusion power plants. Therefore, it will be necessary to minimize tritium losses to the surrounding systems, such as the tritium breeding modules, plasma-facing components, cooling system, etc ...
R. Arredondo, K. Schmid, I. Ricapito, A. Lukenskas, G.A. Spagnuolo   +4 more
doaj   +1 more source

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

IEEE 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, Alessandro Del Nevo, Pietro Arena, Gaetano Bongiovi, Gianfranco Caruso, Pietro Alessandro di Maio, Giuseppe di Gironimo, Marica Eboli, Nicola Forgione, Ruggero Forte, Fabio Giannetti, Giovanni Mariano, Emanuela Martelli, Fabio Moro, Rocco Mozzillo, Andrea Tarallo, Rosaria Villari   +16 more
openaire   +4 more sources

Experimental and Numerical Results of LIFUS5/Mod3 Series E Test on In-Box LOCA Transient for WCLL-BB

Energies, 2021
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, Francesco Galleni, Nicola Forgione, Nicolò Badodi, Antonio Cammi, Alessandro Del Nevo   +5 more
doaj   +1 more source

R&D Needs for the Design of the EU-DEMO HCPB ICD Balance of Plant in FP9

Journal of Nuclear Engineering, 2022
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, Evaldas Bubelis, Wolfgang Hering, Luciana Barucca   +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)

Mechanical 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, Marica EBOLI, Antonio CAMMI, Alessandro DEL NEVO   +3 more
doaj   +1 more source

Manufacturing of PAV-ONE, a Permeator against Vacuum Mock-Up with Niobium Membrane

Energies, 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, Alessandro Venturini, Gianfranco Caruso, Serena Bassini, Chiara Ciantelli, Angela Fiore, Vincenzo Cuzzola, Antonio Denti, Marco Utili   +8 more
doaj   +1 more source

DEMO WCLL breeding zone cooling system design: Analysis and discussion [PDF]

, 2019
The Water-Cooled Lithium-Lead (WCLL) Breeding Blanket (BB) is a key component in charge of ensuring Tritium self-sufficiency, shielding the Vacuum Vessel and removing the generated power of DEMO reactor.
Edemetti F., Tassone A., Caruso G., Martelli E., Nevo A. D.   +4 more
core   +2 more sources

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

Energies, 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, Fabio Giannetti, Alessandro Del Nevo, Gianfranco Caruso   +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

Energies, 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, Alessandro Venturini, Daniele Martelli, Marco Utili   +3 more
doaj   +1 more source

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

Energies, 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, Christian Vorpahl, Christian Bachmann, Francisco A. Hernández, Alessandro Del Nevo   +4 more
doaj   +1 more source