During the JET Preliminary Tritium Experiment (PTE), an estimated 2x1012 Bq (1.1x1021 atoms) of tritium was injected into the JET vacuum vessel. A series of experiments was performed whose purpose was to deplete the torus of tritium, to compare the effectiveness of different methods of tritium removal, and to obtain a quantitative understanding of the processes involved. The effectiveness of the cleaning procedures was such that the normal tokamak programme was resumed one week after the PTE and routing of exhaust gases to atmosphere after two weeks. The release of tritium from the vessel was found to scale with the deuterium release from the vessel, suggesting that dilution and mixing of the hydrogen isotopes in the vessel walls is important. High density, disruptive tokamak discharges were found to be the most successful plasma pulses for tritium removal. Purges with deuterium gas were also effective and have the advantage of operational simplicity. Helium discharges, on the other hand, resulted in low tritium release from the vessel walls. It was demonstrated that the tritium release rate could be predicted using data from hydrogen to deuterium changeover experiments. Using the superior quality of data available from the tritium clean-up experiment, the physical mechanisms necessary to describe the hydrogenic uptake and release from the JET torus were identified. The release of tritium is reproduced using a model which incorporates implantation into a thin surface layer as well as diffusion of tritium into and out of the bulk material.