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 +9 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 ...
Marton Szogradi, Sixten Norrman
doaj +11 more sources
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
The DEMO Water-Cooled Lead–Lithium Breeding Blanket: Design Status at the End of the Pre-Conceptual Design Phase [PDF]
Applied Sciences, 2021 The Water-Cooled Lead–Lithium Breeding Blanket (WCLL BB) is one of the two blanket concept candidates to become the driver blanket of the EU-DEMO reactor. The design was enacted with a holistic approach. The influence that neutronics, thermal-hydraulics (
Pietro Arena +15 more
doaj +4 more sources
Design of a Prototypical Mock-Up for the Experimental Investigation of WCLL First-Wall Performances [PDF]
Energies, 2023 A large research effort is currently ongoing within the framework of the EUROfusion consortium for the study and design of a water-cooled lithium–lead (WCLL) breeding blanket (BB).
Pietro Maccari +4 more
doaj +3 more sources
Exploratory Thermo-Mechanical Assessment of the Bottom Cap Region of the EU DEMO Water-Cooled Lead Lithium Central Outboard Blanket Segment [PDF]
Applied Sciences, 2023 The Water-Cooled Lead Lithium (WCLL) Breeding Blanket (BB) is one of the two BB concept candidates to be selected as the driver blanket for the EU DEMO fusion reactor.
Gaetano Bongiovì +6 more
doaj +3 more sources
Thermomechanical and Thermofluid-Dynamic Coupled Analysis of the Top Cap Region of the Water-Cooled Lithium Lead Breeding Blanket for the EU DEMO Fusion Reactor [PDF]
Energies, 2023 In the EU, the Water-Cooled Lithium Lead (WCLL) Breeding Blanket (BB) concept is one of the candidates for the design of the DEMO reactor. From the past campaign of analysis emerged that the thermal-induced stress led to the failure in the verification ...
Alberto Gioè +9 more
doaj +3 more sources
European DEMO Fusion Reactor: Design and Integration of the Breeding Blanket Feeding Pipes [PDF]
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 +4 more
doaj +6 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
W-HYDRA: a new experimental platform for the Water-Cooled Lead Lithium Breeding Blanket [PDF]
Nuclear FusionIn the framework of the activities coordinated by the EUROfusion consortium, the Water thermal-HYDRAulic (W-HYDRA) experimental platform is being built at the ENEA Brasimone Research Centre in order to support the development of the Water-Cooled Lead ...
P. Arena +14 more
doaj +3 more sources