AbstractThe Tokamak Fusion Test Reactor (TFTR) at Princeton began operation in December 1982. While it has operated succesfully with protium and deuterium achieving record energy confinement time and record ion temperatures. TFTR's ultimate goal is to achieve the scientific break even point of Q = 1 for which deuterium/tritium injection is needed. This paper will discuss the design parameters resulting from using tritium as a fuel, the design and operating philosophies employed, the additional systems and equipment required, the effect on the heating, ventilating and air conditioning systems, the tritium monitoring system and the personnel training.