Results 141 to 150 of about 933 (168)

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.
Francesco Edemetti, Alessandro Del Nevo, Gianfranco Caruso   +2 more
exaly   +5 more sources

DEMO WCLL breeding zone cooling system design: Analysis and discussion [PDF]

Fusion Engineering and Design, 2019
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.
Francesco Edemetti, Emanuela Martelli, Alessandro Tassone   +2 more
exaly   +4 more sources

Pre-analysis of the WCLL breeding blanket mock-up neutronics experiment at the frascati neutron generator

Fusion Engineering and Design, 2020
The Water Cooled Lithium Lead (WCLL) is one of the breeding blanket (BB) concept candidate for the future European Demonstration Fusion Power Reactor (DEMO).
D Flammini, M Angelone, Barbara Caiffi   +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.
Francesco Edemetti, Ivan Di Piazza, Alessandro Del Nevo   +2 more
exaly   +2 more sources

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Tritium transport in HCLL and WCLL DEMO blankets

Fusion Engineering and Design, 2016
Abstract 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, M Utili, M Zucchetti
exaly   +2 more sources

Power plant conceptual study—WCLL concept

Fusion Engineering and Design, 2003
Abstract 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.
Sardain, P., Michel, B., Giancarli, L., Li Puma, A., Poitevin, Y., Szczepanski, J., Maisonnier, D., Ward, D., Fischer, U., Pereslavtsev, P., Natalizio, A., Collen, J., Orden Martinez, A.   +12 more
openaire   +4 more sources

Nuclear analysis of the Single Module Segment WCLL DEMO

Fusion Engineering and Design, 2019
Abstract 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 ...
Simone Noce, F Moro, Francesco Romanelli   +2 more
exaly   +4 more sources

Assessment of activated corrosion products for the DEMO WCLL

Fusion Engineering and Design, 2018
Abstract 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 ...
L Di Pace
exaly   +2 more sources

The fracture mechanics behaviour of the WCLL blanket segment

Fusion Engineering and Design, 2000
The 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

Influence of hydrogen trapping on WCLL breeding blanket performances

Nuclear Fusion, 2021
Tritium 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, Delaporte-Mathurin, Rémi, Charles, Yann, Hodille, Etienne, Grisolia, Christian, Mougenot, Jonathan   +5 more
openaire   +3 more sources