Abstract
A wall model developed for the analysis of Tore Supra wall loading experiments has been applied to an experiment on DIII-D which demonstrated a substantial capacity for retention of deuterium gas in an all-graphite environment, and which showed the efficacy of the pumped divertor to deplete a gas-loaded wall. The Tore Supra model has been extended and applied to evaluate the particle exchange mechanisms between the core, divertor, and wall. Data-constrained plasma modeling is done for the discharges of the load/unload sequence. The poloidal distribution of the charge exchange flux profile to the divertor and outer wall is determined from the Eirene neutral transport code, to estimate the effective working areas for particle exchange and saturation. The deposition and saturation of the hydrogenic efflux in the aC:H layer and graphite is modeled with the I-D WDIFFUSE code, applied to the regions fuelled by charge exchange flux to predict the instantaneous local wall recycling coefficient. A mechanism is proposed to explain the previous paradoxical result that exhaust quickly ( ∼ 3 s) balances the only particle input, due to beam fueling, whereas a long term net wall depletion is observed over ∼ 10 discharges. The saturation and depletion of wall layers fuelled by energetic charge exchange particles provides such a mechanism.
Original language | English |
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Pages (from-to) | 612-617 |
Number of pages | 6 |
Journal | Journal of Nuclear Materials |
Volume | 241-243 |
DOIs | |
State | Published - Feb 11 1997 |
Funding
* Corresponding author. Tel.: + 1-423 574 1349; fax: + 1-423 576 7926; e-mail: [email protected] This research was sponsored in part by the Office of Fusion Energy, U.S. Department of Energy, under contract DE-ACOS-840 R214 °° with Martin Marietta Energy Systems, Inc.
Keywords
- Active pumping
- DIII-D
- Tokamak
- Wall pumping