Design of the national compact stellarator experiment (NCSX)

详细信息    查看全文

• 作者：Nelson ; B.E. ; Berry ; L.A. ; Brooks ; A.B. ; Cole ; M.J. ; Chrzanowski ; J.C. ; Fan ; H.-M. ; Fogarty ; P.J. ; et. al.
• 关键词：Stellarator experiment ; Coil systems ; Compact stellarators ; Modular coils
• 刊名：Fusion Engineering and Design
• 出版年：2003
• 出版时间：September, 2003
• 年：2003
• 卷：66-68
• 期：Complete
• 页码：169-174
• 全文大小：552 K

文摘

The National Compact Stellarator Experiment (NCSX) [http://www.pppl.gov/ncsx/Meetings/CDR/CDRFinal/EngineeringOverview_R2.pdf] is being designed as a proof of principal test of a quasi-axisymmetric compact stellarator. This concept combines the high beta and good confinement features of an advanced tokamak with the low current, disruption-free characteristics of a stellarator. NCSX has a three-field-period plasma configuration with an average major radius of 1.4 m, an average minor radius of 0.33 m and a toroidal magnetic field on axis of up to 2 T. The stellarator core is a complex assembly of four coil systems that surround the highly shaped plasma and vacuum vessel. Heating is provided by up to four, 1.5 MW neutral beam injectors and provision is made to add 6 MW of ICRH. The experiment will be built at the Princeton Plasma Physics Laboratory, with first plasma expected in 2007.