Andrea Batti
System-level hydraulic modelling of the PbLi loop for the Breeding Blanket of a tokamak.
Rel. Antonio Froio, Laura Savoldi, Roberto Zanino. Politecnico di Torino, Corso di laurea magistrale in Ingegneria Energetica E Nucleare, 2020
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Abstract
The breeding blanket (BB) is a key part of future fusion reactors. Its purposes are: 1) absorbing the energy from neutrons produced in the plasma by the fusion nuclear reactions between deuterium and tritium (D-T), 2) breeding further tritium fuel and 3) shielding other radiation-susceptible components. The Water-Cooled Lithium-Lead (WCLL) is one of the candidate design options for the European DEMO nuclear fusion reactor. The current design is based on pressurized water as coolant, liquid lithium-lead (PbLi) as breeder-multiplier and EUROFER as structural material. However, this design is in a pre-conceptual phase and it is important to analyze with numerical models the behavior of the system from the different points of view, e.g.
neutronics, thermal-mechanics and thermal-hydraulics
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