Modeling of tritium retention in TFTR

The tritium retention experience of the Tokamak Fusion Test Reactor (TFTR) is reviewed and the data related to models of plasma surface interactions. Over 3.5 years of TFTR DT 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. Go-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. (C) 1999 Elsevier Science B.V. All rights reserved.