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Experimental exploration of profile control in the Princeton Beta Experiment-Modified (PBX-M) tokamak

Journal Article · · Physics of Fluids B; (United States)
DOI:https://doi.org/10.1063/1.860744· OSTI ID:6423061
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  1. Princeton University, Plasma Physics Laboratory, Forrestal Campus, P. O. Box 451, Princeton, New Jersey 08543 (United States)
  2. Department of Applied Physics, Columbia University, 206 SW Mudd Building, New York, New York, 10027 (United States)
  3. EURATOM-ENEA sulla Fusione, CRE Frascati, C.P. 65, 00044-Frascati, Rome (Italy)
  4. Fusion Physics and Technology, 3547 Voyager Street, Suite 104, Torrance, California 90503-1673 (United States)
  5. JET Joint Undertaking, Abingdon
The experimental program of the Princeton Beta Experiment-Modified (PBX-M) tokamak [Phys. Fluids B[bold 2], 1271 (1990)] is directed toward tailoring plasma profiles to achieve greater stability and confinement and to gain access to the second stability region. Modification of the current density profile has been achieved with lower-hybrid current drive (LHCD), leading to a regime free of global magnetohydrodynamic modes, while raising the value of [ital q](0) above unity. The diffusion of the fast electrons produced by LHCD has been examined using two-dimensional hard x-ray imaging. Ion Bernstein waves (IBW) have been used for ion heating: a preliminary analysis shows that ion heating was spatially localized and in agreement with theoretical calculations. Divertor biasing has modified the electric field inside the last closed surface, resulting in the formation of a transport barrier, which in turn has reduced the threshold power of neutral beam injection (NBI) for H-mode transition by 25%.
DOE Contract Number:
AC02-76CH03073
OSTI ID:
6423061
Journal Information:
Physics of Fluids B; (United States), Journal Name: Physics of Fluids B; (United States) Vol. 5:7; ISSN 0899-8221; ISSN PFBPEI
Country of Publication:
United States
Language:
English