The Fusion Record — Fusion Energy News ← Home · Knowledge base
Machines & Facilities

Princeton Large Torus (PLT)

The first tokamak to heat plasma to 60 million degrees — proving auxiliary heating could push fusion toward ignition temperatures.

Reviewed Last reviewed: 9 Aug 2026 · Category: Machines & Facilities

The Princeton Large Torus, known universally as PLT, was the flagship American tokamak of the late 1970s and the machine that first demonstrated thermonuclear-class ion temperatures in a magnetically confined plasma. Operating at the Princeton Plasma Physics Laboratory (PPPL) from 1975 to 1986, PLT reached ion temperatures exceeding 60 million degrees Celsius in 1978 — a milestone that proved auxiliary heating could overcome the limitations of ohmic heating and bring fusion within practical reach.

Design and Construction

PLT was a medium-sized tokamak with a major radius of 1.32 m and a minor radius of 0.40 m. It produced a toroidal magnetic field of up to 3.2 T and carried plasma currents as high as 700 kA. The vacuum vessel was circular in cross-section with a molybdenum or carbon limiter defining the plasma boundary. PLT was designed from the outset to accommodate powerful neutral beam injection (NBI) systems — a deliberate strategy to test whether external heating could break through the temperature ceiling that ohmic heating alone could not penetrate.1

PLT was the direct descendant of Princeton's converted Model C stellarator (renamed the Symmetric Tokamak, or ST), which itself was built in response to the T-3 results from Moscow.

The 60-Million-Degree Milestone

In 1978, PLT's neutral beam injectors delivered up to 3 MW of heating power into the plasma, driving ion temperatures to approximately 60 million degrees (about 5 keV) — the threshold generally considered necessary for deuterium-tritium fusion. This was the first time any magnetic confinement device had achieved such temperatures and represented a factor-of-five increase over what ohmic heating alone could produce in the same machine.2

The result was transformative for the field. It demonstrated conclusively that neutral beam injection was a viable path to fusion-relevant temperatures, validating a technology that would become standard equipment on every subsequent large tokamak including TFTR, JET, JT-60, and ITER.3

Additional Contributions

Beyond its headline temperature record, PLT made significant contributions to plasma physics. It was among the first tokamaks to study the effects of impurity transport and radiation losses systematically. Experiments with different limiter materials — tungsten, carbon, and molybdenum — provided critical data on plasma-wall interactions that informed the design of the next generation of machines. PLT also conducted early radiofrequency heating experiments, including ion cyclotron resonance heating (ICRH) and lower hybrid current drive, pioneering techniques that remain central to tokamak operations today.4

PLT's neutral beam results directly justified the construction of TFTR at Princeton — the machine that would go on to produce 10.7 MW of fusion power from deuterium-tritium reactions in 1994.

PLT operated until 1986, when it was decommissioned to make room for TFTR operations and diagnostics. Its legacy is embedded in every modern tokamak's heating portfolio: the principle that external power can push a confined plasma to fusion temperatures, first demonstrated on PLT, underpins the entire ITER burning-plasma strategy.5

Sources

  1. Eubank, H. et al., 'PLT Neutral Beam Heating Results,' Physical Review Letters, Vol. 43, No. 4, pp. 270–274, 1979.
  2. Princeton Plasma Physics Laboratory, 'PLT: Princeton Large Torus,' PPPL Historical Records.
  3. Goldston, R.J. and Rutherford, P.H., 'Introduction to Plasma Physics,' CRC Press, 1995.
  4. Hosea, J. et al., 'Fast-Wave Heating of Two-Ion Plasmas in PLT,' Physical Review Letters, Vol. 43, No. 15, 1979.
  5. Strachan, J.D. et al., 'Impurity Transport in PLT,' Nuclear Fusion, Vol. 22, No. 8, 1982.

Related