Impurity behavior during ion-Bernstein wave heating in PBX-M [electronic resource].
- Washington, D.C. : United States. Dept. of Energy, 1994. and Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- 5 pages : digital, PDF file
- Additional Creators:
- Oak Ridge National Laboratory, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
- Restrictions on Access:
- Free-to-read Unrestricted online access
- Ion-Bernstein-wave heating (IBWH) has been tested in several tokamaks. In some cases the results have been quite positive, producing temperature increases and also improving both energy and particle confinement times, whereas in others, no distinctive changes were observed. Most recently, IBWH has been utilized in the Princeton Beta Experiment-Modified (PBX-M) where the long-range goal is the achievement of operation in the second stable region by current and pressure profile control. Investigations have been performed in this machine using IBWH as the sole source of auxiliary power or using IBWH in conjunction with neutral-beam injection (NBI) or with lower-hybrid current drive (LHCD). Impurity studies seem particularly important for IBWH since not only have influxes often been observed to increase, but the global impurity confinement time has also been shown to lengthen as the confinement of the working gas improved. The authors present here a set of characteristic experimental results regarding the impurity behavior in PBX-M; in general, these are consonant with previous observations in other tokamaks.
- Published through SciTech Connect., 09/01/1994., "conf-940635--13", "DE94018114", European conference on controlled fusion and plasma physics,Marseilles (France),26 Jun - 1 Jul 1994., and Bell, R.; Ono, M.; LeBlanc, B.P.; Post-Zwicker, A.P.; Kugel, H.W.; Tighe, W.; Kaita, R.; Paul, S.F.; Isler, R.C.
- Funding Information:
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