Published 1978 | Version v1
Report Restricted

Plasma confinement and impurity flow reversal experiments in the ISX-A Tokamak

Creators

Description

This paper describes experimental studies of behaviors of impurities and their effects on plasma confinement in ISX-A, a tokamak with circular cross section of moderate size and relatively low toroidal field, B/sub T/ equal to or less than 15 kG. The confinement studies investigated plasma behaviors (especially effects of impurities on plasma confinement) under a wide range of discharge conditions, wall cleanliness (discharge cleaning vs titanium gettering), limiter materials (stainless steel vs carbon or molybdenum), plasma ''fueling'' methods (gas puffing vs pellet injection), and working gases (hydrogen vs deuterium). Optimum confinement parameters (tau/sub E/ = 32 msec, Z/sub eff/ = 1.5) resulted in a stainless steel limiter and titanium gettering

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.

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Additional details

Publishing Information

Imprint Pagination
14 p.
Report number
IAEA-CN--37-N-4

Conference

Title
7. conference on plasma physics and control.
Dates
23 - 31 Aug 1978.
Place
Innsbruck, Austria.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
10446861
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CLEANING; CONFINEMENT; FUEL PELLETS; GASES; IMPURITIES; ISX TOKAMAK; REACTOR FUELING
Descriptors DEC
CLOSED PLASMA DEVICES; FLUIDS; THERMONUCLEAR DEVICES; TOKAMAK DEVICES

Optional Information

Secondary number(s)
CONF-780811--22.