Magnetic confinement fusion research is a quite fertile field nowadays. A new tokamak machine will be built in Frascati (Italy) in the next few years, in the framework of the Divertor Tokamak Test project. Toroidal field coils will be manufactured by ASG Superconductors (Genoa, Italy) and design tables are currently being accomplished. The creation of a full-size joint sample is scheduled in the near future for the process qualification. The present work has the aim to individuate, where present, probable critical issues of the future joint/termination boxes (and hence of the coil), from the point of view of hydraulic performances and electric DC resistance. A study has been carried out on main hydraulic and electric issues of previously manufactured joints for fusion machines. Two spreadsheets have been developed to evaluate Void Fraction parameter and the coolant pressure loss across the conductor or the joint box. Experimental hydraulic measurements have been performed on CICCs and joint samples. Some electrical considerations have been carried out basing on resistance and geometrical data of few past joint boxes.
La fusione nucleare a confinamento magnetico è attualmente un campo di ricerca piuttosto florido. Un nuovo tokamak sarà costruito a Frascati (Italia) nei prossimi anni, all’interno del progetto Divertor Tokamak Test. Le bobine toroidali verranno realizzate da ASG Superconductors (Genova, Italia), attualmente la progettazione costruttiva è in via di ultimazione. La creazione di un full-size sample delle giunzioni è prevista quanto prima per la completa qualifica del processo. Il presente elaborato ha l’obiettivo di individuare, ove presenti, probabili criticità delle future giunzioni o terminazioni (e dunque dell’intera bobina), dal punto di vista delle performance idrauliche e di quelle elettriche. E’ stato condotto uno studio sui principali problemi idraulici ed elettrici di giunzioni di precedenti macchine a fusione. Due fogli di calcolo sono stati sviluppati, per valutare la void fraction e per predire la caduta di pressione del refrigerante all’interno di cavi o giunzioni. Sono state condotte misurazioni sperimentali legate al problema idraulico, sia su CICCs sia su scatole di giunzione. Alcune considerazioni elettriche sono state fatte partendo dai dati disponibili sulla resistenza elettrica e sui parametri geometrici relativi ad altre giunzioni.
Study of hydraulic and electric issues of resistive joints for magnetic fusion toroidal and poloidal field coils
SORANO, ALESSANDRO
2021/2022
Abstract
Magnetic confinement fusion research is a quite fertile field nowadays. A new tokamak machine will be built in Frascati (Italy) in the next few years, in the framework of the Divertor Tokamak Test project. Toroidal field coils will be manufactured by ASG Superconductors (Genoa, Italy) and design tables are currently being accomplished. The creation of a full-size joint sample is scheduled in the near future for the process qualification. The present work has the aim to individuate, where present, probable critical issues of the future joint/termination boxes (and hence of the coil), from the point of view of hydraulic performances and electric DC resistance. A study has been carried out on main hydraulic and electric issues of previously manufactured joints for fusion machines. Two spreadsheets have been developed to evaluate Void Fraction parameter and the coolant pressure loss across the conductor or the joint box. Experimental hydraulic measurements have been performed on CICCs and joint samples. Some electrical considerations have been carried out basing on resistance and geometrical data of few past joint boxes.File | Dimensione | Formato | |
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https://hdl.handle.net/10589/196714