DocumentCode
433829
Title
Manufacturing development of the NCSX modular coil winding forms and vacuum vessel
Author
Heitzenroeder, P. ; Brown, T. ; Neilson, G.H. ; Reiersen, W. ; Viola, M. ; Malinowski, F. ; Sutton, L. ; Cole, M. ; Nelson, B. ; Williamson, D. ; Goranson, P. ; Keilbach, R.
Author_Institution
Princeton Plasma Phys. Lab., NJ, USA
fYear
2003
fDate
14-17 Oct. 2003
Firstpage
276
Lastpage
279
Abstract
The National Compact Stellarator Experiment (NCSX) is the first of a new class of stellarators known as "compact stellarators". Stellarators are characterized by three dimensional magnetic fields and plasma shapes and are the best-developed class of magnetic fusion devices after the tokamak. Stellarators are attractive because they solve critical problems of magnetic fusion energy: steady state operation without current drive and stable operation without feedback control or rotation drive. The differentiating feature of the compact stellarator is the use of a small plasma current in conjunction with external magnetic fields to provide the required plasma shaping and confinement. This permits a more compact stellarator design. Many of the components of NCSX are conventional in design and manufacture; however, two of the most critical components, the vacuum vessel and the modular coil winding forms, are also the most challenging components to manufacture. This paper describes design of these two critical elements of NCSX and the three-phase program that is being used in the manufacturing development of these components.
Keywords
Tokamak devices; electromagnets; fusion reactor design; fusion reactor operation; machine components; plasma toroidal confinement; plasma transport processes; stellarators; windings; NCSX modular coil winding form; National Compact Stellarator Experiment; compact stellarator design; external magnetic fields; magnetic fusion devices; magnetic fusion energy; manufacturing development; plasma confinement; plasma current; plasma shapes; stable operation; steady state operation; three dimensional magnetic fields; tokamak; vacuum vessel; Coils; Magnetic confinement; Magnetic devices; Magnetic fields; Manufacturing; Plasma confinement; Plasma devices; Plasma materials processing; Plasma stability; Shape;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on
Print_ISBN
0-7803-7908-X
Type
conf
DOI
10.1109/FUSION.2003.1426638
Filename
1426638
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