Modeling of Tritium Retention in TFTR
- Princeton Plasma Physics Laboratory
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.
- Research Organization:
- Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ
- Sponsoring Organization:
- USDOE Office of Energy Research (ER)
- DOE Contract Number:
- AC02-76CH03073
- OSTI ID:
- 2683
- Report Number(s):
- PPPL-3311; ON: DE00002683
- Country of Publication:
- United States
- Language:
- English
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