Search citation statements
Paper Sections
Citation Types
Publication Types
Relationship
Authors
Journals
A6s/rm-The Large l l c l i r a l Device (LIID) or Nalional Institute for Fusion Science (NIFS) is a heliolron-type experimental fusion device which has lhr capability ofranlining current-less and steady-state plasma. The primary feature on the engineering aspect of LHD i s using supcrranducling coils for magnetic eanlinemmc W O pod boiling helical coils (HI, H2) and three pairs of forced-flow poloidal coils (IV. IS, OV) wound with cable-in-conduit conductors (CICC). The maximum magnetic field a1 plasma center Is 3 T in Phase I experiment and 4 T in Phase 11, while its stored rncrgy becomes 0.9 GJ and 1.6 GJ, rcspeetively. These coils are eonneeted to the power supplies by superconducling bus-lines with their nominal current af31.3 kA. The construction of LHD started in 1991 and wss completed by the end of 1997. During this period, extensive research m d devrlopmrnt were conducted lo romplete a large-scale suprrcandurting system. The plasma experiment slarled on March 31. 1998 and four plasma erperimentrl campaigns have been performed sucressfully in thrcc years. The lifth eyrle operation started in August 2001. The knowledge which has been acquired during the design, devclopmrnt, and operation of superconducting system for LHD, is summarized. I. 1NlUODUCTlON ATIONAL Institute for Fusion Science (NIFS) was established m 1989 as an inter-university research institute in Japan. To study the science o f nuclear fusion and its application for the realization o f a future nuclear fusion reactor, the Large Helical Device (LHD) project has been undertaken at NIFS [I]. The LHD is an experimental fusion device which uses the heliotron magnetic field concept developed in Japan. To confine current-less steady-state plasma, LHD was designed as a fully superconducting system consisting oftwo helical coils, three pairs o f poloidal coils and superconducting bus-lines. The construction o f LHD started in 1991 as manufacturing the helical coil winding machine, the I V poloidal coil, and the LHD main experimental building. Extensive research'and development have been required to construct a large-scale superconducting system for LHD, such as highly stable superconductors, winding techniques of helical coils with complicated three-dimensional configuration, forced-flow poloidal coils with NbTi cable-in-conduit conductor (CICC), flexible superconducting bus-lines, and so on. The LHD construction was completed by the end o f 1997 as an eight-year project.for Phase I experiment. The plasma experiment was started on March 31, 1998, just as originally scheduled at the beginning [2]. Since then, four cycles of N . . ' 332-6 Oroshi, Toki, Gifu 509-5292, Japan plasma experimental campaigns have been performed in threc years and we have already succeeded to obtain high plasma parameters such as I O keV o f electron temperature. 5 keV o f ion temperature and beta value o f 3.5 %, which substantially exceed those obtained by the previous helical type devices. 11. DESIGN AND DEVELOPMENTOF LHD A. Overview ofLHD Fig. I shows the LHD cryostat sur...
A6s/rm-The Large l l c l i r a l Device (LIID) or Nalional Institute for Fusion Science (NIFS) is a heliolron-type experimental fusion device which has lhr capability ofranlining current-less and steady-state plasma. The primary feature on the engineering aspect of LHD i s using supcrranducling coils for magnetic eanlinemmc W O pod boiling helical coils (HI, H2) and three pairs of forced-flow poloidal coils (IV. IS, OV) wound with cable-in-conduit conductors (CICC). The maximum magnetic field a1 plasma center Is 3 T in Phase I experiment and 4 T in Phase 11, while its stored rncrgy becomes 0.9 GJ and 1.6 GJ, rcspeetively. These coils are eonneeted to the power supplies by superconducling bus-lines with their nominal current af31.3 kA. The construction of LHD started in 1991 and wss completed by the end of 1997. During this period, extensive research m d devrlopmrnt were conducted lo romplete a large-scale suprrcandurting system. The plasma experiment slarled on March 31. 1998 and four plasma erperimentrl campaigns have been performed sucressfully in thrcc years. The lifth eyrle operation started in August 2001. The knowledge which has been acquired during the design, devclopmrnt, and operation of superconducting system for LHD, is summarized. I. 1NlUODUCTlON ATIONAL Institute for Fusion Science (NIFS) was established m 1989 as an inter-university research institute in Japan. To study the science o f nuclear fusion and its application for the realization o f a future nuclear fusion reactor, the Large Helical Device (LHD) project has been undertaken at NIFS [I]. The LHD is an experimental fusion device which uses the heliotron magnetic field concept developed in Japan. To confine current-less steady-state plasma, LHD was designed as a fully superconducting system consisting oftwo helical coils, three pairs o f poloidal coils and superconducting bus-lines. The construction o f LHD started in 1991 as manufacturing the helical coil winding machine, the I V poloidal coil, and the LHD main experimental building. Extensive research'and development have been required to construct a large-scale superconducting system for LHD, such as highly stable superconductors, winding techniques of helical coils with complicated three-dimensional configuration, forced-flow poloidal coils with NbTi cable-in-conduit conductor (CICC), flexible superconducting bus-lines, and so on. The LHD construction was completed by the end o f 1997 as an eight-year project.for Phase I experiment. The plasma experiment was started on March 31, 1998, just as originally scheduled at the beginning [2]. Since then, four cycles of N . . ' 332-6 Oroshi, Toki, Gifu 509-5292, Japan plasma experimental campaigns have been performed in threc years and we have already succeeded to obtain high plasma parameters such as I O keV o f electron temperature. 5 keV o f ion temperature and beta value o f 3.5 %, which substantially exceed those obtained by the previous helical type devices. 11. DESIGN AND DEVELOPMENTOF LHD A. Overview ofLHD Fig. I shows the LHD cryostat sur...
scite is a Brooklyn-based organization that helps researchers better discover and understand research articles through Smart Citations–citations that display the context of the citation and describe whether the article provides supporting or contrasting evidence. scite is used by students and researchers from around the world and is funded in part by the National Science Foundation and the National Institute on Drug Abuse of the National Institutes of Health.
hi@scite.ai
10624 S. Eastern Ave., Ste. A-614
Henderson, NV 89052, USA
Copyright © 2024 scite LLC. All rights reserved.
Made with 💙 for researchers
Part of the Research Solutions Family.