From 1993 to 1997, TFTR achieved a significant milestone by becoming the world's first magnetic confinement fusion device to perform extensive experiments with plasmas composed of 50/50 deuterium and tritium. This marked a critical step in fusion research, moving beyond deuterium-only plasmas to investigate the physics and engineering challenges associated with the most efficient fusion fuel cycle. The experiments were designed to gather data on plasma performance, confinement, and neutron production under conditions relevant to future fusion power plants. The successful operation of TFTR with D-T fuel provided invaluable insights into plasma behavior at higher temperatures and densities, directly informing the design and operational strategies for subsequent fusion devices.

During its D-T campaign, TFTR achieved a peak fusion power output of 10.7 MW. This was accomplished using a toroidal magnetic field strength of 2.0 T and a plasma current of 2.0 MA. The experiments involved injecting deuterium and tritium gases into the tokamak, where they were heated to temperatures exceeding 300 million degrees Celsius. The high-energy fusion reactions produced helium nuclei and fast neutrons, which were measured by various diagnostic instruments. The ability to sustain and control these high-power D-T plasmas was a testament to the advanced engineering and plasma control systems developed for TFTR.

This was accomplished using a toroidal magnetic field strength of 2.0 T and a plasma current of 2.0 MA.

The TFTR D-T experiments yielded crucial data on plasma confinement and transport properties under fusion-relevant conditions. Researchers observed that the confinement of energetic alpha particles, the fusion products of D-T reactions, was consistent with theoretical predictions. Furthermore, the experiments provided detailed measurements of neutron flux and energy spectra, which were essential for validating neutron transport codes and understanding neutron activation of the reactor vessel. The data collected also contributed to the understanding of tritium retention and handling, a key challenge for future D-T fusion power plants.

Prior to its D-T operations, TFTR had a long history of plasma physics research, beginning operations in 1982. It was instrumental in developing and testing advanced magnetic confinement concepts, including the use of high-temperature superconducting magnets and innovative plasma heating techniques. The transition to D-T fuel was a carefully planned phase, building upon years of operational experience and diagnostic development. The facility was extensively modified to handle tritium, a radioactive isotope of hydrogen, and to manage the increased neutron flux and associated activation of machine components. This meticulous preparation was vital for the safety and success of the D-T experiments.

The legacy of TFTR's D-T experiments is profound, directly influencing the design and operational planning for international fusion projects like ITER and various private fusion ventures. The data gathered on plasma performance, neutronics, and tritium handling remains a cornerstone for fusion energy development. Future research will continue to build upon these foundational results, focusing on achieving sustained net energy gain and developing robust power plant technologies. The insights gained from TFTR's D-T campaign continue to guide the global pursuit of fusion power.

The TFTR D-T campaign achieved a peak fusion power of 10.7 MW, with a plasma current of 2.0 MA and a toroidal magnetic field of 2.0 T. The experiments ran from 1993 to 1997, with the final D-T shot occurring in October 1997. The device was a tokamak, a magnetic confinement fusion device that uses powerful magnetic fields to contain and control a superheated plasma. The primary goal of the D-T campaign was to study the physics of burning plasmas, where the fusion reactions themselves contribute significantly to heating the plasma. This was a critical step towards demonstrating the feasibility of fusion as a power source.