DC power system for superconducting fusion test facility LHD

Author

Chikaraishi, H. ; Tanahashi, S. ; Yamada, S. ; Motojima, O. ; Satoh, T. ; Niwa, H. ; Uede, T. ; Hiue

Author_Institution

Nat. Inst. for Fusion Sci., Gifu, Japan

Volume

2

fYear

1997

fDate

3-6 Aug 1997

Firstpage

747

Abstract

The Large Helical Device (LHD) is a fusion plasma test facility that has three sets of superconducting helical coils and three sets of superconducting poloidal coils. This paper introduces a power system to excite these coils. The system consists of large current thyristor rectifiers, quench protection circuits, control system and superconducting DC power feeders. Several components are developed for this power system. A DC circuit breaker using a small power fuse and a vacuum circuit breaker realize a compact and low cost quench protection circuit. A superconducting DC power feeder, that joins the power supply and a coil, moves a large cryogenic joint box to far away from the LHD main structure

Keywords

electric fuses; power supplies to apparatus; rectifying circuits; stellarators; superconducting coils; thyristor convertors; vacuum circuit breakers; DC circuit breaker; DC power system; Large Helical Device; control system; cryogenic joint box; current thyristor rectifiers; power fuse; quench protection circuits; superconducting DC power feeders; superconducting fusion test facility; superconducting helical coils; superconducting poloidal coils; vacuum circuit breaker; Circuit breakers; Control systems; Fuses; Plasma devices; Power system protection; Power systems; Rectifiers; Superconducting coils; Test facilities; Thyristors;

fLanguage

English

Publisher

ieee

Conference_Titel

Power Conversion Conference - Nagaoka 1997., Proceedings of the

Conference_Location

Nagaoka

Print_ISBN

0-7803-3823-5

Type

conf

DOI

10.1109/PCCON.1997.638304

Filename

638304