Elsevier

Journal of Nuclear Materials

Volumes 266–269, 2 March 1999, Pages 1303-1308
Journal of Nuclear Materials

The effect of lithium wall conditioning in TFTR on plasma–surface interactions

https://doi.org/10.1016/S0022-3115(98)00863-0Get rights and content

Abstract

Five TFTR deuterium supershots with increasing Li pellet injection are analyzed in detail. Five chords of experimental H-α measurements are compared to predictions from a series of computational models. First, experimental data from the discharge is used in the TRANSP plasma transport code to predict the ion flux to the wall. Then a modified version of the DEGAS neutral transport code which includes both reflection, desorption and sputtering of hydrogenic species from the wall is used to determine the neutral density profile across the machine. This data combined with the known density and temperature contours predicts values for the magnitude of H-α light observed for 16 viewing angles of the diagnostic. To match the experimental data, the wall reflection, desorption and sputtering coefficients were altered using data from VFTRIM-3D to include the effect of the added Li. In addition, the first 10 cm of the stainless steel wall adjoining the C inner bumper limiter was treated as C-covered; the highest flux area of the inner wall was treated as a sink; and the lower reflection coefficients for a Li-wall rather than a C-wall were used over an increasingly larger area of the inner wall as the Li concentration in the discharges increased.

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)

  • R.V. Budny et al.

    J. Nucl. Mater.

    (1992)
  • D. Heifetz et al.

    J. Comput. Phys.

    (1982)
  • D.N. Ruzic

    Nucl. Instrum. Methods B

    (1990)
  • J.D. Strachan, et al., Phys. Rev. Lett. 72 (1994)...
There are more references available in the full text version of this article.

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