The Design of Water Loop Facility for Supporting the WCLL Breeding Blanket Technology and Safety [PDF]
Energies, 2023 The WCLL Breeding Blanket of DEMO and the Test Blanket Module (TBM) of ITER require accurate R&D activities, i.e., concept validation at a relevant scale and safety demonstrations. In view of this, the strategic objective of the Water Loop (WL) facility,
Bruno Gonfiotti +2 more
exaly +10 more sources
Design of the Test Section for the Experimental Validation of Antipermeation and Corrosion Barriers for WCLL BB [PDF]
Applied Sciences (Switzerland), 2022 Tritium permeation into the Primary Heat Transfer System (PHTS) of DEMO and ITER reactors is one of the challenging issues to be solved in order to demonstrate the feasibility of nuclear fusion power plants construction.
Luigi Candido +2 more
exaly +6 more sources
Magneto-Convective Analyses of the PbLi Flow for the EU-WCLL Fusion Breeding Blanket
Energies, 2021 The Water Cooled Lithium Lead (WCLL) breeding blanket is one of the driver blanket concepts under development for the European Demonstration Reactor (DEMO). The majority of the blanket volume is occupied by flowing PbLi at eutectic composition.
Fernando Roca Urgorri +1 more
exaly +4 more sources
Model Development and Transient Analysis of the WCLL BB BOP DEMO Configuration Using the Apros System Code [PDF]
Energies, 2021 Extensive modelling and analytical work has been carried out considering the water-cooled lithium–lead breeding blanket (WCLL BB) balance of plant (BOP) configuration of the demonstration power plant (DEMO) using the Apros system code, developed by VTT ...
Sixten Norrman
exaly +4 more sources
Conceptual Design of the Steam Generators for the EU DEMO WCLL Reactor
Energies, 2023 In the framework of the EUROfusion Horizon Europe Programme, ENEA and its linked third parties are in charge of the conceptual design of the steam generators belonging to EU DEMO WCLL Breeding Blanket Primary Heat Transfer Systems (BB PHTSs).
Cristiano Ciurluini +2 more
exaly +5 more sources
Design of a Test Section for the Experimental Investigation of the WCLL Manifold Hydraulic Features
Energies, 2023 A scaled-down test section representative of an Outboard Segment manifold of the Water-Cooled Lithium Lead Breeding Blanket for the European DEMO has been designed for installation and test in a high- mass flow branch of the W-HYDRA facility, under ...
Laura Savoldi +2 more
exaly +4 more sources
Oxidation behaviour of EUROFER-97 under simulated water-cooled lithium lead breeder blanket conditions [PDF]
npj Materials DegradationThe effect of water chemistry, surface condition, alkalizing agent (LiOH vs. KOH), and Zn addition was investigated at 300 °C on the oxidation behaviour of reduced activation ferritic martensitic (RAF/M) EUROFER-97.
Liberato Volpe +4 more
doaj +2 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).
Alessandro del Nevo +2 more
exaly +3 more sources
Energies, 2023 The latest progress in the design of the water-cooled lithium–lead (WCLL) tritium extraction and removal (TER) system for the European DEMO tokamak reactor is presented.
Laura Savoldi +2 more
exaly +3 more sources
Energies, 2023 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.
Andrea Zappatore, Antonio Froio
exaly +3 more sources