The effect of lithium wall conditioning in TFTR on plasma–surface interactions
Introduction
The performance of TFTR is greatly enhanced when the carbon inner bumper limiter has been scoured of its imbedded D by the repeated production of high power discharges fueled only by the desorbed gas. When Zeff reaches a value of approximately 6 all of the easily desorbed surface D has been removed. The wall is then fully conditioned and a `supershot' plasma is formed [1].
In May 1994, a series of supershots were performed keeping all parameters constant except for the addition of Li pellets. The first shot of the series had no Li injection and served as a baseline. The subsequent four shots had the same amount of Li injected into each, thus increasing the total Li content on the walls during the series. The performance of the plasma improved as the total Li content increased. This paper endeavors to explain why in terms of the plasma-surface interactions.
The primary diagnostic used in this work is a spectroscopic measurement of the H-α light emanating from differing chords across the minor radius of the plasma. This data is compared to modeling results for the discharge. In previous work a variety of plasma parameters in the models were altered 2, 3to produce a fit to the data. Changes of that type were inadequate to match the data from these experiments. In this work the only variables changed in the model are the plasma–surface interaction of the ions and neutrals on the walls. These variables include the absorption/re-emission characteristics, the sputtering coefficient of trapped D, and the reflection coefficients.
Section snippets
Simulation
The TRANSP plasma analysis code is used to model the time evolution of the plasma parameters 3, 4. The energy, particle, and magnetic field dynamics are computed based on the measured plasma profiles and location of the last closed flux surface. The measured inputs include time-dependent profiles of the electron density, electron and carbon temperatures, and carbon toroidal velocity. The plasma scrape-off length used in TRANSP was held constant in all cases at 1.60 cm.
These measured parameters
Experiment
The five TFTR discharges examined in this study are # 76649, 76650, 76651, 76653 and 76654 from May 23, 1994. These TFTR supershots were performed after a long series of wall conditioning which desorbed the inner bumper limiter of deuterium. Supershots are circular cross-section plasmas which ride on the inner bumper limiter and are only fueled by the neutral beams. Therefore the interaction with the wall dominates recycling. There was no Li injection in the first shot and then two identical
Results
The presence of increasing accumulated Li on the walls had several effects. First, the Zeff at 4.2 s increased from 2.3 to 3.0. This increase is inevitable with the addition of an impurity. However, the plasma performance improved dramatically. The total stored energy increased from 3 to 4.5 MJ. The central electron line density at that time also increased from 2.5 to 3.9 × 1019 m−3 due to a peaking of the density profile. The peak electron density (at r/a=0) rose from 5.1 to 6.5 × 1019 m−3 while
Conclusion
The wall model chosen has a significant impact on both “I” and being able to match the experimental HAIFA data. To properly include the effect of conditioning, absorption only occurs on the segments that have the highest ion flux. This conditioning does not remove all of the embedded D, since the sputtering of D from those areas is essential to produce a good fit to the data. Once Li is added absorption on the high-particle-flux-receiving segments remains strong since Li also can trap
Acknowledgements
This work was supported under the TFTR collaborators program, subcontract DOE PPPL S-03991-G.
References (9)
- et al.
J. Nucl. Mater.
(1992) - et al.
J. Comput. Phys.
(1982) Nucl. Instrum. Methods B
(1990)- J.D. Strachan, et al., Phys. Rev. Lett. 72 (1994)...
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