DocumentCode
2758501
Title
NCSX Construction Progress and Research Plans
Author
Neilson, G.H. ; Heitzenroeder, P. ; Lyon, J. ; Nelson, B. ; Reiersen, W. ; Zarnstorff, M. ; Brooks, A. ; Brown, T. ; Cole, M. ; Chrzanowski, J. ; Fogarty, P. ; Gettelfinger, G. ; Goranson, P. ; Raftopoulos, S. ; Schmidt, J. ; Stratton, Brian ; Simmons, Ro
Author_Institution
Princeton Plasma Phys. Lab., NJ
fYear
2005
fDate
Sept. 2005
Firstpage
1
Lastpage
6
Abstract
Stellarators use 3D plasma and magnetic field shaping to produce a steady-state disruption-free magnetic confinement configuration. Compact stellarators have additional attractive properties-quasi-symmetric magnetic fields and low aspect ratio. The National Compact Stellarator Experiment (NCSX) is being constructed at the Princeton Plasma Physics Laboratory (PPPL) in partnership with the Oak Ridge National Laboratory (ORNL) to test the physics of a high-beta compact stellarator with a low-ripple, tokamak-like magnetic configuration. The engineering challenges of NCSX stem from its complex geometry requirements. These issues are addressed in the construction project through manufacturing R&D and system engineering. As a result, the fabrication of the coil winding forms and vacuum vessel are proceeding in industry without significant technical issues, and preparations for winding the coils at PPPL are in place. Design integration, analysis, and dimensional control are functions provided by system engineering to ensure that the finished product will satisfy the physics requirements, especially accurate realization of the specified coil geometries. After completion of construction in 2009, a research program to test the expected physics benefits will start
Keywords
fusion reactor design; plasma toroidal confinement; stellarators; 3D plasma; NCSX; National Compact Stellarator Experiment; Oak Ridge National Laboratory; Princeton Plasma Physics Laboratory; R&D engineering; coil winding forms; complex geometry requirements; construction progress; design integration; high-beta compact stellarator; low effective ripple; quasisymmetric magnetic fields; steady-state disruption-free magnetic confinement configuration; system engineering; tokamak-like magnetic configuration; toroidal magnetic plasma; vacuum vessel; Coils; Geometry; Laboratories; Magnetic fields; Physics; Plasma confinement; Plasma properties; Steady-state; Systems engineering and theory; Testing; NCSX; construction; design; stellarator;
fLanguage
English
Publisher
ieee
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
Type
conf
DOI
10.1109/FUSION.2005.252851
Filename
4018885
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