JT60SA, the superconducting tokamak under construction in Japan, will be equipped with a mix of new and reused Power Supplies (PS). Most of the new PS are procured by European Voluntary Contributors under the framework of Broader Approach agreement between F4E and JAEA. For the toroidal circuit, the 6 pulses ac/dc converter will be procured by CEA. It is rated 25.7kA and 80V dc, and will work in steady state condition. For the poloidal circuits the procurement of ten new ac/dc converters, rated ±20kA and about ±1kV is shared between CEA and ENEA. They are 24 pulses four quadrant converters, with back to back thyristor bridges. In order to allow a smooth crossing of zero current, a particular control mode with circulating current operation will be implemented. The fast control of plasma position is obtained by two in-vessel coils supplied with independent thyristor converters procured by ENEA, each one rated ± 5kA and ±1kV. Plasma initiation requires a fast variation of current in the Central Solenoids, obtained with the insertion of a settable resistor in series to the coils. This is achieved with the operation of four Switching Network Units procured by ENEA, producing up to 5kV at the nominal current of 20 kA. The protection of superconducting magnets, both toroidal and poloidal, is assured by thirteen Quench Protection Circuits procured by Consorzio RFX, rated ±20kA and ±3.8 kV for poloidal QPCs and 25.7kA and 2.8kV for toroidal ones: in case of coil quench or other fault requiring a fast de-magnetization of the coils, each QPC inserts in the circuit a dump resistor discharging the energy stored in the coils. Finally the suppression of RWM is actively performed by 18 in-vessel coils, independently supplied by a corresponding number of IGBT inverters procured by Consorzio RFX, characterized by high dynamic performances and low latency of 50 ?s, and rated for 300A and 240V. The present status of the aforementioned PS is described in the paper: their detailed design has been completed and some systems have been already manufactured and tested.

Present status of the new Power Supply Systems of JT-60SA procured by EU

Elena Gaio;
2014

Abstract

JT60SA, the superconducting tokamak under construction in Japan, will be equipped with a mix of new and reused Power Supplies (PS). Most of the new PS are procured by European Voluntary Contributors under the framework of Broader Approach agreement between F4E and JAEA. For the toroidal circuit, the 6 pulses ac/dc converter will be procured by CEA. It is rated 25.7kA and 80V dc, and will work in steady state condition. For the poloidal circuits the procurement of ten new ac/dc converters, rated ±20kA and about ±1kV is shared between CEA and ENEA. They are 24 pulses four quadrant converters, with back to back thyristor bridges. In order to allow a smooth crossing of zero current, a particular control mode with circulating current operation will be implemented. The fast control of plasma position is obtained by two in-vessel coils supplied with independent thyristor converters procured by ENEA, each one rated ± 5kA and ±1kV. Plasma initiation requires a fast variation of current in the Central Solenoids, obtained with the insertion of a settable resistor in series to the coils. This is achieved with the operation of four Switching Network Units procured by ENEA, producing up to 5kV at the nominal current of 20 kA. The protection of superconducting magnets, both toroidal and poloidal, is assured by thirteen Quench Protection Circuits procured by Consorzio RFX, rated ±20kA and ±3.8 kV for poloidal QPCs and 25.7kA and 2.8kV for toroidal ones: in case of coil quench or other fault requiring a fast de-magnetization of the coils, each QPC inserts in the circuit a dump resistor discharging the energy stored in the coils. Finally the suppression of RWM is actively performed by 18 in-vessel coils, independently supplied by a corresponding number of IGBT inverters procured by Consorzio RFX, characterized by high dynamic performances and low latency of 50 ?s, and rated for 300A and 240V. The present status of the aforementioned PS is described in the paper: their detailed design has been completed and some systems have been already manufactured and tested.
2014
Istituto gas ionizzati - IGI - Sede Padova
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.14243/282279
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