Modeling of Tritium Retention in TFTR
Authors: C.H. Skinner, J.T. Hogan, J.N. Brooks, W. Blanchard, R.V. Budny, J. Hosea, D. Mueller, A. Nagy, and D.P. Stotler
The Tokamak Fusion Test Reactor (TFTR) tritium retention experience is reviewed and the data related to models of plasma surface interactions. Over 3.5 years of TFTR deuterium-tritium operations, approximately 51% of the tritium injected into TFTR was retained in the torus. Most of this was subsequently recovered by glow discharges and air ventilation. Co-deposition rates for representative conditions in tritium operation were modeled with the BBQ code. The calculations indicate that known erosion mechanisms and subsequent co-deposition are sufficient to account for the order of magnitude of retention.