DocumentCode :
2154087
Title :
Design and analysis of the modular coils for the National Compact Stellarator Experiment (NCSX)
Author :
Williamson, D. ; Brooks, A. ; Cole, M. ; Fan, H.-M. ; Fogarty, P. ; Nelson, B. ; Strickler, D. ; Reiersen, W.
Author_Institution :
Oak Ridge Nat. Lab., TN, USA
fYear :
2002
fDate :
2002
Firstpage :
418
Lastpage :
421
Abstract :
The National Compact Stellarator Experiment (NCSX) is proposed as a test of a low aspect ratio, quasi-axisymmetric plasma configuration that exhibits high beta and good confinement in a disruption-free environment. The experiment will be built at Princeton Plasma Physics Laboratory (PPPL) and utilize some ancillary equipment. The NCSX stellarator core is a complex assembly of four coil systems which provide the magnetic field for plasma shaping and position control, inductive current drive, and field error correction. The primary magnets are the modular coils, which provide up to 2-T at an average major radius of 1.4-m. Other magnets include toroidal field (TF) coils, poloidal field (PF) coils, and trim coils, which can be used to control resonant field errors. The magnets are supported by an integral shell structure, which also serves as the winding form for the modular coils. The coils and structure have been evaluated for thermal stress and electromagnetic loads during normal operating conditions. The results indicate that the performance of the modular coil system is acceptable.
Keywords :
coils; electromagnets; fusion reactor design; fusion reactor operation; physical instrumentation control; plasma toroidal confinement; stellarators; thermal stresses; 1.4 m; 2 T; NCSX; National Compact Stellarator Experiment; PPPL; Princeton Plasma Physics Laboratory; coil systems; confinement; disruption-free environment; electromagnetic load; field error correction; inductive current drive; integral shell structure; low aspect ratio quasiaxisymmetric plasma configuration; magnetic field; modular coils; plasma shaping; position control; primary magnets; resonant field errors; stellarator core; thermal stress; trim coils; Coils; Error correction; Laboratories; Magnetic confinement; Magnetic cores; Magnets; Physics; Plasma confinement; Testing; Thermal stresses;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering, 2002. 19th Symposium on
Print_ISBN :
0-7803-7073-2
Type :
conf
DOI :
10.1109/FUSION.2002.1027726
Filename :
1027726
Link To Document :
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