Title :
Operations of LHD
Author_Institution :
Nat. Inst. for Fusion Sci., Nagoya, Japan
fDate :
30 Sep-5 Oct 1995
Abstract :
The Large Helical Device (LHD) is a big non-tokamak type superconducting toroidal fusion apparatus, which is an on-going project under construction being completed in 1997. Based on the results of the developments in both areas of the physics and technology researches concerned, the LHD project is expected to contribute to the necessary understandings of the currentless steady-state plasmas, which have a high performance of temperature, density, confinement time and beta value extrapolatable to the reactor regime (Q~0.35). This paper describes the necessary issues of the major engineering operations scenarios of LHD, which are especially concerned with the SC magnet technology, the expected SC coil performance and obtained technological flexibility, the required functions for the coil power supply and protection circuit, the system control, and the developed closed divertor system for the edge control
Keywords :
fusion reactor design; fusion reactor operation; fusion reactors; plasma density; plasma temperature; plasma toroidal confinement; power supplies to apparatus; superconducting coils; superconducting magnets; LHD operations; Large Helical Device; beta value; closed divertor system; confinement time; currentless steady-state plasmas; edge control; engineering operations; magnet technology; nontokamak type superconducting toroidal fusion apparatus; plasma density; plasma temperature; protection circuit; superconducting coil performance; superconducting coil power supply; system control; Coils; Control systems; Inductors; Magnetic confinement; Physics; Plasma confinement; Plasma density; Plasma temperature; Steady-state; Superconducting magnets;
Conference_Titel :
Fusion Engineering, 1995. SOFE '95. Seeking a New Energy Era., 16th IEEE/NPSS Symposium
Conference_Location :
Champaign, IL
Print_ISBN :
0-7803-2969-4
DOI :
10.1109/FUSION.1995.534268
