National Spherical Torus Experiment (NSTX)

Ono, Masayuki

Princeton University. Plasma Physics Laboratory.

关键词: Research Programs;    Plasma Diagnostics;    70 Plasma Physics And Fusion Technology;    Plasma Heating;    Operation;   

DOI  :  10.2172/754424
RP-ID  :  PPPL-3445
RP-ID  :  AC02-76CH03073
RP-ID  :  754424

美国|英语

来源: UNT Digital Library

【 摘 要 】

The main aim of National Spherical Torus Experiment (NSTX) is to establish the fusion physics principles of the innovative spherical torus (ST) concept. Physics outcome of the NSTX research program is relevant to near-term applications such as the Volume Neutron Source (VNS) and burning plasmas, and future applications such as the pilot and power plants. The NSTX device began plasma operations in February 1999 and the plasma current was successfully ramped up to the design value of 1 million amperes (MA) on December 14, 1999. The CHI (Coaxial Helicity Injection) and HHFW (High Harmonic Fast Wave) experiments have also started. Stable CHI discharges of up to 133 kA and 130-msec duration have been produced using 20 kA of injected current. Using eight antennas connected to two transmitters, up to 2 MW of HHFW power was successfully coupled to the plasma. The Neutral-beam Injection (NBI) heating system and associated NBI-based diagnostics such as the Charge-exchange Recombination Spectrometer (CHERS) will be operational in October 2000.