Fabia Schito
Thermal-hydraulic and thermo-mechanical analysis and design optimization of the neutralizer for the Neutral Beam Injection system of the Divertor Tokamak Test (DTT) facility.
Rel. Roberto Bonifetto, Roberto Zanino, Giorgio Zavarise, Andrea Zappatore. Politecnico di Torino, Corso di laurea magistrale in Ingegneria Meccanica, 2021
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Abstract
Nuclear fusion promises to be a sustainable, reliable and safe energy source. In Italy, the DTT S.c.a.r.l. is actively engaged on this front with a project, proposed by ENEA and supported by EUROfusion, which has as its goal the construction, at the ENEA research center in Frascati, of a tokamak fusion experiment, aimed at testing possible solutions for the divertor, one if not the most critical component of ITER (under construction in Cadarache, France) and of the subsequent European DEMO. The main objective of the divertor is the mitigation of the power exhaust issue, due to the enormous thermal heat flux carried to the walls by the plasma particles.
A key role inside the tokamak is played by the high-energy neutral beam injection system (NBI), necessary to heat the plasma to an operating temperature of about 100 million degrees
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