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NSTX began operation in September 1999. As described below, the NSTX research team has made excellent progress in exploring the characteristics and effectiveness of the ST configuration and in resolving scientific issues relevant for ITER and future fusion devices. In the process, the team has implemented numerous improvements in measurement and operational capabilities thereby opening the door to future progress in ST research.

2008  First-of-a-kind high spatial resolution measurements on NSTX confirm the existence of a long-theorized form of plasma turbulence driven by variation of the electron temperature across the plasma. These tiny swirls of turbulence in the plasma may be one cause of the long standing mystery of electron heat loss.
2007  The evaporation of lithium coatings on plasma facing components in NSTX is shown to improve plasma confinement and to prevent instabilities called Edge-Localized Modes.
2006  A 160-thousand-ampere plasma current is initiated in NSTX without induction from its central solenoid. This world records is attained using a technique known as Coaxial Helicity Injection.
2005  NSTX researchers develop methods to sustain high beta by employing a set of small magnetic coils, controlled by feedback, to counteract the growth of certain instabilities.
2004  NSTX achieves a record toroidal beta of 40%, three times the best values achieved in conventional tokamaks. Beta relates to the economics of fusion power production.
2002  A combination of neutral-beam-driven and self-generated “bootstrap current” in NSTX provides about 60% of the total plasma current, thereby relaxing the need for induction to sustain the current.