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Impurity behavior during ion-Bernstein wave heating in PBX-M

Technical Report ·
DOI:https://doi.org/10.2172/10180377· OSTI ID:10180377
;  [1]; ; ; ; ; ; ;  [2]
  1. Oak Ridge National Lab., TN (United States). Fusion Energy Div.
  2. Princeton Plasma Physics Lab., NJ (United States)
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.
Research Organization:
Oak Ridge National Lab., TN (United States)
Sponsoring Organization:
USDOE, Washington, DC (United States)
DOE Contract Number:
AC05-84OR21400
OSTI ID:
10180377
Report Number(s):
CONF-940635--13; ON: DE94018114
Country of Publication:
United States
Language:
English