Tritium retention at the wall is an important consideration for the operation of a fusion ignition experiment. In this paper, the fusion ignition experiment IGNITEX is considered and tritium implantation, retention, and removal from the first wall are investigated. For the analysis, a new implantation model is used. The implantation model incorporates analytical fits to detailed Monte Carlo calculations of the implantation profile. The Monte Carlo calculations include the effect of the surface floating potential on the ion distribution function at the plasma-surface interface. Tritium retention at the first wall is shown to increase with incident fluence until saturation occurs. The isotope-exchange process for use in tritium removal at the wall is studied.