Helium transport in enhanced confinement regimes on the TEXTOR and DIII-D tokamaks

D. L. Hillis, J. T. Hogan, K. H. Finken, W. P. West, R. R. Weynants, M. R. Wade, K. Akaishi, W. Y. Baek, J. Boedo, K. H. Burrell, R. W. Conn, K. H. Dippel, R. Doerner, H. Euringer, D. Finkenthal, D. S. Gray, C. M. Greenfield, P. Gohil, R. J. Groebner, J. KimC. C. Klepper, A. M. Messiaen, P. K. Mioduszewski, A. Miyahara, R. Moyer, G. Van Oost, A. Pospieszcyk, D. Reiter, D. Rusbüldt, R. P. Seraydarian, R. Van Nieuwenhove, G. H. Wolf

Research output: Contribution to journalArticlepeer-review

21 Scopus citations

Abstract

Comparisons of helium (He) transport and exhaust in L-mode and in an enhanced confinement regime (H-mode), which is induced by a polarizing electrode, have been made for the TEXTOR tokamak. The results show an increased tendency for He accumulation when bulk plasma energy and particle confinement are improved during the polarization-induced H-mode. Since these results imply that a high He pumping efficency may be necessary for H-mode burning plasmas, we have begun exploring He transport in a divertor H-mode, similar to that proposed for the international thermonuclear experimental reactor (ITER). A collaborative program has been initiated to measure He transport and scaling on DIII-D during L-mode, H-mode, and ELMing H-mode plasma conditions. To simulate the presence of He ash in DIII-D, a 25 ms He puff is injected into a DIII-D plasma, resulting in a He concentration of ≈5%. The time dependence of the He2+ density profiles in the plasma core is measured by charge-exchange recombination spectroscopy at 11 radial locations.

Original languageEnglish
Pages (from-to)35-44
Number of pages10
JournalJournal of Nuclear Materials
Volume196-198
Issue numberC
DOIs
StatePublished - Dec 1 1992

Funding

For future steady-state tokamaks, such as the international thermonuclear experimental reactor (ITER), continuous purging of the helium (He) ash is essential. Estimates \[1\]s how that newly created He ions must be removed within 7 to 15 energy confinement times to maintain continuous reactor operation (r~e/r E < 7- 15). Recent measurements \[2-6\] on TEXTOR and other tokamaks demonstrate that He can be readily transported from the plasma core during L-mode plasma discharges. TEXTOR experiments use the advanced limiter test-II (ALT-II) system, a toroidal belt * Research sponsored in part by the Office of Fusion Energy, US Department of Energy, under contract DE-AC06-84OR21400 with Martin Marietta Energy Systems, Inc., and by the US Department of Energy under contract DE-AC03-89ER51114.

FundersFunder number
US Department of EnergyDE-AC03-89ER51114, DE-AC06-84OR21400
Fusion for Energy

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