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
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