Alfredo Pagliaro , Francesco Braghin , Alessandro Bruschi , Daniele Busi , Eliana De Marchi , Francesco Fanale , Gustavo Granucci , Afra Romano , Fabio Zanon
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引用次数: 0
Abstract
The steerable launcher mirrors, essential for directing microwave beams into the plasma, play a pivotal role in the Electron Cyclotron Resonance Heating (ECRH) system of the Divertor Tokamak Test (DTT) facility, currently under construction in Frascati, Italy. Due to the substantial heat loads acting on the mirrors, internal water-cooling channels are necessary to control temperature and deformation. A variable-depth complementary spiral cooling channel was considered in this study. A dielectric material with high thermal conductivity was selected as a potential candidate to reduce eddy currents, this mitigating magnetic torques and mechanical stress, while guaranteeing adequate cooling. Thermo-structural simulations (FSI) were conducted to assess the mirror's resistance to induced stresses, its deformations, and cooling performance. A transient analysis showed that thermal steady-state is the worst-case thermal loading condition during the entire experiment. Additionally, the thermo-structural behavior of various materials was analyzed to demonstrate the superior performance of the selected dielectric material. The cooling channel was subsequently adapted to a prototype mirror, on which CFD and FSI simulations were performed to validate the numerical model against future real-world experiments. Finally, crack propagation analysis confirmed the feasibility of using technical ceramics for the launching mirror, paving the way for dielectric materials in the ECRH system of DTT.
期刊介绍:
The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.