The NSTX Upgrade research program consists of several
overlapping and complementary mission elements:

  • Advance the spherical tokamak (ST) as a candidate for a Fusion Nuclear Science Facility (FNSF), i.e. a ST-FNSF



  • Develop solutions for the plasma-material interface, including the snowflake divertor and lithium / liquid metal plasma facing components (PFCs)

  • Advance toroidal confinement physics predictive capability for ITER and beyond


  • Develop the ST for fusion energy production, for example in an ST Pilot Plant