Title :
Challenges in Designing the Modular Coils for the National Compact Stellarator Experiment (NCSX)
Author :
Williamson, D. ; Brooks, A. ; Brown, T. ; Chrzanowski, J. ; Cole, M. ; Fan, H.-M. ; Freudenberg, K. ; Fogarty, P. ; Hargrove, T. ; Heitzenroeder, P. ; Lovett, G. ; Nelson, B. ; Raftopolous, S. ; Reiersen, W. ; Stratton, B. ; Strickler, D.
Author_Institution :
Oak Ridge Nat. Lab., TN
Abstract :
The National Compact Stellarator Experiment (NCSX) is a quasi-axisymmetric plasma experiment that combines the high beta and good confinement of an advanced tokamak with the low current, disruption-free characteristics of a stellarator. The experiment is based on a three field-period plasma configuration with an average major radius of 1.4 m, a minor radius of 0.3 m, and a toroidal magnetic field on axis of up to 2 T. The modular coils are one set in a complex assembly of four coil systems that surround the highly shaped plasma. There are six each of three coil types in the assembly, for a total of 18 modular coils. The coils are constructed by winding copper cable onto a cast stainless steel winding form that has been machined to high accuracy, so that the current center of the winding pack is within +/-1.5 mm of its theoretical position. The modular coils operate at a temperature of 80 K and are subjected to rapid heating and stress during a pulse. The final coil design has presented many challenges with its requirements for winding accuracy, good thermal performance, a robust supporting structure, and ease of assembly and maintenance
Keywords :
Tokamak devices; coils; fusion reactor design; fusion reactor ignition; fusion reactor materials; plasma heating; plasma instability; plasma toroidal confinement; stellarators; windings; 0.3 m; 1.4 m; NCSX; National Compact Stellarator Experiment; cast stainless steel winding form; coil design; copper cable; disruption-free characteristics; low current characteristic; modular coils; quasiaxisymmetric plasma experiment; rapid heating; robust supporting structure; stellarator; stress; thermal performance; three field-period plasma configuration; tokamak; toroidal magnetic field; winding accuracy; winding pack; Assembly systems; Coils; Copper; Machine windings; Magnetic confinement; Plasma confinement; Plasma properties; Steel; Tokamaks; Toroidal magnetic fields; Stellarator; design; electromagnetic; modular coil;
Conference_Titel :
Fusion Engineering 2005, Twenty-First IEEE/NPS Symposium on
Conference_Location :
Knoxville, TN
Print_ISBN :
0-4244-0150-X
Electronic_ISBN :
0-4244-0150-X
DOI :
10.1109/FUSION.2005.252889