Results 61 to 70 of about 506,130 (104)

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

Modelling WCLL breeder blankets

, 2021
International audienceThe key purpose of DEMO is to provide electricity from fusion power. An integral part to this design will be the tritium breeding blanket. Accurate modelling of hydrogen transport and inventories within the breeder blanket component
Grisolia, Christian, Dark, James, Charles, Y., Mougenot, Jonathan, Hodille, Etienne,, Delaporte-Mathurin, Rémi, Hodille, Etienne, A   +6 more
core   +3 more sources

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

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

Nuclear 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

Energies, 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, Pierdomenico Lorusso, Pietro Arena, Marica Eboli, Ranieri Marinari, Amelia Tincani, Cristiano Ciurluini, Fabio Giannetti, Nicolò Badodi, Claudio Tripodo, Antonio Cammi, Luciana Barucca, Andrea Tarallo, Pietro Agostini, Alessandro Del Nevo   +14 more
doaj   +1 more source

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

Applied 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, Marica Eboli, Antonio Cammi, Alessandro Del Nevo   +3 more
doaj   +1 more source

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

Applied 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