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