Design of the national compact stellarator experiment (NCSX)

摘要: Abstract 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 quasi-axisymmetric compact stellarator. This concept combines the high beta and good confinement features an advanced tokamak with low current, disruption-free characteristics NCSX has three-field-period plasma configuration average major radius 1.4 m, minor 0.33 m toroidal magnetic field on axis up to 2 T. stellarator core complex assembly four coil systems that surround highly shaped vacuum vessel. Heating provided by four, 1.5 MW neutral beam injectors provision made add 6 ICRH. experiment will be built at Princeton Plasma Physics Laboratory, first expected in 2007.