Embrittlement of WCLL blanket and its fracture mechanical assessment [PDF]
Nuclear Fusion, 2023 In the European fusion programme, the Water Cooled Lithium Lead breeding blanket (WCLL BB) uses EUROFER as a structural material cooled with water at temperatures between 295 °C–328 °C and a pressure of 155 bar.
Jarir Aktaa +7 more
doaj +6 more sources
NUCLEAR DATA SENSITIVITY/UNCERTAINTY PRE-ANALYSIS OF FNG WCLL FUSION BENCHMARK [PDF]
EPJ Web of Conferences, 2021 To assure tritium self-sufficiency in future fusion reactors such as DEMO the accuracy of TRP calculations has to be demonstrated within the design uncertainties.
Kodeli Ivan A. +2 more
doaj +3 more sources
Magneto-Convective Analyses of the PbLi Flow for the EU-WCLL Fusion Breeding Blanket [PDF]
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 R. Urgorri +2 more
doaj +2 more sources
Design of a Test Section for the Experimental Investigation of the WCLL Manifold Hydraulic Features [PDF]
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 ...
Aldo Collaku +4 more
doaj +2 more sources
Design of the Test Section for the Experimental Validation of Antipermeation and Corrosion Barriers for WCLL BB [PDF]
Applied Sciences, 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.
Marco Utili +5 more
doaj +2 more sources
3D Transient CFD Simulation of an In-Vessel Loss-of-Coolant Accident in the EU DEMO WCLL Breeding Blanket [PDF]
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.
Mauro Sprò +2 more
doaj +2 more sources
Numerical Simulation of an Out-Vessel Loss of Coolant from the Breeder Primary Loop Due to Large Rupture of Tubes in a Primary Heat Exchanger in the DEMO WCLL Concept [PDF]
Energies, 2021 This work presents a thermohydraulic analysis of a postulated accident involving the rupture of the breeder primary cooling loop inside a heat exchanger (once through steam generator).
Francesco Galleni +4 more
doaj +2 more sources
Experimental and Numerical Results of LIFUS5/Mod3 Series E Test on In-Box LOCA Transient for WCLL-BB [PDF]
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 +5 more
doaj +2 more sources
DEMO WCLL breeding zone cooling system design: Analysis and discussion
Fusion Engineering and Design, 2019 Abstract 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. The last function is fulfilled by two independent cooling systems: First Wall (FW) that removes the plasma heat flux and Breeding Zone (BZ)
Francesco Edemetti +4 more
openalex +3 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