The Infona portal uses cookies, i.e. strings of text saved by a browser on the user's device. The portal can access those files and use them to remember the user's data, such as their chosen settings (screen view, interface language, etc.), or their login data. By using the Infona portal the user accepts automatic saving and using this information for portal operation purposes. More information on the subject can be found in the Privacy Policy and Terms of Service. By closing this window the user confirms that they have read the information on cookie usage, and they accept the privacy policy and the way cookies are used by the portal. You can change the cookie settings in your browser.
As a flexible and controllable auxiliary heating method, electron cyclotron resonance heating and current drive has been widely used in various plasma confinement devices and also will be used on J-TEXT. The main parts of the J-TEXT electron cyclotron systems under development are donated by the Culham Science Center, including six 60 GHz/200 kW/5 s (0.5 s) gyrotrons, six magnets and auxiliary power...
High DC current interruption system and large energy dissipation system are required for the protection of ITER superconductive coils. The ITER superconducting magnets will store up to 56 GJ of magnetic energy per operation cycle. In case of coil quench and other fault conditions the energy stored in the coils must be discharged quickly and safely within a discharge time constant from 7.5 to 14 second...
The Large Helical Device (LHD) is a helical-type fusion plasma experimental device using six superconducting coils to form a magnetic field. The fundamental operation of the LHD is performed under a dc magnetic field, and a power system which was suitable for steady state excitation was designed and constructed. With the progress in the fusion plasma research, dynamic experiments such as sweep of...
This paper briefly describes the ITER Project, introducing the harnessing of the nuclear fusion process and how the tokamak is configured to achieve this. The magnet circuit power supply systems are described in more detail concentrating on the electrical engineering, control and interlock aspects.
The Korea Superconducting Tokamak Advanced Research (KSTAR) device is an advanced superconducting tokamak to establish scientific and technological bases for an attractive fusion reactor. This device requires 3.5 Tesla of toroidal field (TF) for plasma confinement, and requires a strong poloidal flux swing to generate an inductive voltage to produce and sustain the tokamak plasma. KSTAR was originally...
The LHD is a helical-type fusion plasma device using six superconducting coils to form a magnetic field. The fundamental operation of the LHD is performed under a dc magnetic field, and a power system which was suitable for steady state excitation was designed and constructed. With the progress in the fusion plasma research, more dynamic experiments are planned, and require dynamic control of magnetic...
Set the date range to filter the displayed results. You can set a starting date, ending date or both. You can enter the dates manually or choose them from the calendar.