Published February 1997 | Version v1
Journal article

Negative magnetic shear modes of operation in the Alcator C-Mod tokamak near the beta limit

  • 1. Massachusetts Inst. of Tech., Cambridge, MA (United States). Plasma Fusion Center
  • 2. Lawrence Livermore National Lab., CA (United States)
  • 3. Princeton Univ., NJ (United States). Plasma Physics Lab.

Description

The stability properties of non-inductively driven, reserved-shear type current profiles that may be achieved for Alcator C-Mod tokamak-like parameters (aspect ratio R/a = 3) are examined. It is found that without a conducting wall, the best stability results (βN up to 3.7) are achieved for highly triangular plasmas (δ = 0.7) at qmin 2.2, for relatively broad pressure profiles (ρ(0)/Pavg = 2.8) and large values of rmin/a ( = 0.75). For elliptical or circular cross-sectional plasmas with little triangularity, the stability limits are significantly lower (βNmax = 2.2). Finally, more-peaked pressure profiles (ρ(0)/Pavg 4.5) have lower beta limits than broader profiles. (Author)

Additional details

Publishing Information

Journal Title
Plasma Physics and Controlled Fusion
Journal Volume
39
Journal Issue
2
Journal Page Range
p. 223-236.
ISSN
0741-3335
CODEN
PPCFET

INIS

Country of Publication
United Kingdom
Country of Input or Organization
United Kingdom
INIS RN
28044365
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Descriptors DEI
ALCATOR DEVICE; BETA RATIO; MAGNETIC FIELDS; OPERATION; SHEAR; STABILITY
Descriptors DEC
CLOSED PLASMA DEVICES; THERMONUCLEAR DEVICES; TOKAMAK DEVICES