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 +4 more
doaj +1 more source
Three-dimensional MHD flow and heat transfer in a channel with internal obstacle [PDF]
, 2018 The magnetohydrodynamic flow and heat transfer of a liquid metal in a channel past a circular cylinder with walls of non-uniform conductivity were investigated. The applied magnetic field was transversal to the forced flow (x-direction) and coplanar with
Caruso, Gianfranco +2 more
core +1 more source
Multiphysics Optimization for First Wall Design Enhancement in Water-Cooled Breeding Blankets [PDF]
, 2021 The commercial feasibility of the first fusion power plant generation adopting D-T plasma is strongly dependent upon the self-sustainability in terms of tritium fuelling. Within such a kind of reactor, the component selected to house the tritium breeding
Chiovaro P. +3 more
core +1 more source
Tritium transport model at the minimal functional unit level for HCLL and WCLL breeding blankets of DEMO [PDF]
Fusion Engineering and Design, 2018 Abstract The Helium-Cooled Lithium-Lead (HCLL) and Water-Cooled Lithium-Lead (WCLL) Breeding Blankets are two of the four European blanket designs proposed for the DEMO reactor. A tritium transport model inside the blanket is fundamental to assess its preliminary design and safety features. Tritium transport and permeation are complex phenomena to be
Candido, Luigi +3 more
core +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).
Marica Eboli +5 more
doaj +1 more source
Embrittlement of WCLL blanket and its fracture mechanical assessment
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 +1 more source
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 +1 more source
Numerical study of laminar magneto-convection in a differentially heated square duct [PDF]
, 2017 Magnetohydrodynamic pressure drops are one of the main issues for liquid metal blanket in fusion reactors. Minimize the fluid velocity at few millimeters per second is one strategy that can be employed to address the problem.
Caruso, Gianfranco +2 more
core +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 +3 more
doaj +1 more source
Structural assessment of the EU-DEMO WCLL Central Outboard Blanket segment under normal and off-normal operating conditions [PDF]
, 2021 Within the framework of the EUROfusion design activities concerning the EU-DEMO Breeding Blanket (BB) system, a research campaign has been carried out at the University of Palermo with the aim of investigating the structural behaviour of the DEMO Water ...
Arena P. +9 more
core +1 more source