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Tritium transport in HCLL and WCLL DEMO blankets
Fusion Engineering and Design, 2016Abstract The Helium-Cooled Lithium Lead (HCLL) and Water-Cooled Lithium Lead (WCLL) Breeding Blankets are two of the four blanket designs proposed for DEMO reactor. The study of tritium transport inside the blankets is fundamental to assess their preliminary design and safety features. A mathematical model has been derived, in a new form making makes
Luigi Candido +2 more
exaly +2 more sources
Thermal-hydraulic analysis of the DEMO WCLL elementary cell: BZ tubes layout optimization
Fusion Engineering and Design, 2020 The Water-Cooled Lithium-Lead (WCLL) Breeding Blanket (BB) is a key component in charge of ensuring Tritium production, shield the Vacuum Vessel and remove the heat generated by plasma thermal radiation and nuclear reactions.
Caruso G +2 more
exaly +2 more sources
Power plant conceptual study—WCLL concept
Fusion Engineering and Design, 2003Abstract A power plant conceptual study (PPCS) has been launched in the framework of the EU fusion program the objective of which is to demonstrate the credibility of fusion power plant design and the claims for safety and environmental advantages and for economic viability of fusion power.
A Li Puma, P Sardain, P Pereslavtsev
exaly +5 more sources
Optimization of the first wall cooling system for the DEMO WCLL blanket [PDF]
Fusion Engineering and Design, 2020 The Water-Cooled Lithium-Lead (WCLL) Breeding Blanket (BB) is a key component in charge of ensuring Tritium production, shield the Vacuum Vessel and remove the heat generated by plasma thermal radiation and nuclear reactions.
Caruso G +2 more
exaly +3 more sources
Influence of hydrogen trapping on WCLL breeding blanket performances
Nuclear Fusion, 2021Tritium transport simulations in Water-Cooled Lithium Lead (WCLL) breeding blankets have been performed with FESTIM. Fluid dynamics and heat transfer were coupled to evaluate how temperature and LiPb velocity fields affect Tritium transport. The 2D WCLL model consisted of tungsten, EUROFER and liquid LiPb. Tritium inventories and permeation fluxes have
Dark, James +5 more
openaire +3 more sources
The fracture mechanics behaviour of the WCLL blanket segment
Fusion Engineering and Design, 2000The fracture mechanics behaviour is a limiting factor for the lifetime of a component, especially when the reduction of toughness of the structural material because of neutron irradiation effect is taken into account. In order to investigate the end of life behaviour of the WCLL blanket segment, a fracture mechanics analysis has been performed ...
Claudio Nardi, A Palmieri
openaire +1 more source
Nuclear analysis of the Single Module Segment WCLL DEMO
Fusion Engineering and Design, 2019Abstract The latest design of the Water Cooled Lithium Lead blanket for the European DEMO reactor is based on a Single Module Segment (SMS) concept for the blanket segments: the removal of the gaps between the modules (present in the former Multi Module structure design), with the consequent reduction of the neutron streaming, improves the tritium ...
Rosaria Villari +2 more
exaly +4 more sources
Assessment of activated corrosion products for the DEMO WCLL
Fusion Engineering and Design, 2018Abstract This paper deals with the assessment of the activated corrosion products (ACPs) for the First Wall water-cooled loop of the DEMO WCLL reactor. The aim was devoted to scan some operating parameters, not yet frozen, which eventually proved to be very important, such as the coolant temperature during plasma dwell, materials for the Steam ...
Di Pace, Luigi, Quintieri, Lina
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Preliminary RAMI analysis of WCLL blanket and breeder systems
Fusion Engineering and Design, 2015Abstract DEMO will be a prototype fusion reactor designed to prove the capability to produce electrical power in a commercially acceptable way. One of the key factors in that endeavor is the achievement of certain level of plant availability. Therefore, RAMI (Reliability, Availability, Maintainability and Inspectability) will be a key element in the ...
Jose Manuel Arroyo +4 more
openaire +1 more source
Investigation on cooling performance of WCLL breeding blanket first wall for EU DEMO
Fusion Engineering and Design, 2019 The Breeding Blanket (BB) First Wall (FW) is the first boundary separating the fusion plasma and its energetic particles from the rest of a Tokamak. The heat load specifications at different poloidal positions are reviewed according to the maximum heat ...
Songlin Liu +2 more
exaly +2 more sources