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Fusion glossary

N

At the Neutral Beam Test Facility at Consorzio RFX, in Padua, Italy, ITER neutral beam injection will be tested in advance of operation on two test beds: SPIDER (an ITER-scale negative ion source) and MITICA (a full-size ITER neutral beam injector). See this ITER webpage.

Flexible superconductor made of niobium titanium compound suitable for use up to 10T with helium coolant at 4.5 K.
When the total power produced during a fusion plasma pulse surpasses the thermal power injected to heat the plasma. See Energy Breakeven.
ITER's heating neutral beam injectors shoot uncharged high-energy particles into the plasma where, by way of chaotic motion and collision, they will transfer their energy to the charged plasma particles and raise plasma temperature.    

NSTX-U is an upgrade of the National Spherical Torus Experiment (NSTX, 1999-2010) located at Princeton Plasma Physics Laboratory (USA). Currently completing repairs, NSTX-U is expected to resume operations in 2025. See this page.