Tritium experience in the Tokamak fusion test reactor

Tritium management is a key enabling element in fusion technology. Tritium fuel was used in 3.5 years of successful DT operations in the Tokamak Fusion Test Reactor at Princeton Plasma Physics Laboratory. The DT campaign enabled TFTR to explore the transport, alpha physics and MHD stability of a reactor core. It also provided experience with tritium retention and removal that highlighted the importance of these issues in future DT machines. In this paper we summarize the tritium retention and removal experience in TFTR and its implications for future reactors. (author)