Published March 2003 | Version v1
Journal article

Heat flux scaling experiments in NSTX

Description

We report the first results of heat flux scaling experiments in National Spherical Torus Experiment (NSTX). We find that the peak heat flux observed in the outer divertor was ∼6 MW/m2 at 5 MW heating power in lower-single-null diverted configuration. The peak heat flux was observed to increase with heating power, and the highest heat fluxes had narrow profile widths. The peak heat flux is lower than predicted by early 2-D edge transport conservative design calculations. However, the total power flow to the divertor is only 15-30% of the input power, suggesting other processes reduce the available open field line power which can be conducted and convected to the target

Additional details

Identifiers

PII
S0022311502014411;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
313-316
Journal Issue
3-4
Journal Page Range
p. 1005-1009
ISSN
0022-3115
CODEN
JNUMAM

Conference

Title
15. international conference on plasma-surface interactions in controlled fusion devices
Acronym
PSI-15
Dates
26-31 May 2002
Place
Gifu (Japan)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
34051070
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DIVERTORS; HEAT FLUX; NSTX DEVICE; PEAK LOAD; PLASMA SCRAPE-OFF LAYER; SCALING; WALL EFFECTS
Descriptors DEC
BOUNDARY LAYERS; CLOSED PLASMA DEVICES; LAYERS; SPHEROMAK DEVICES; THERMONUCLEAR DEVICES; TOKAMAK DEVICES

Optional Information

Copyright
Copyright (c) 2003 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.
Collaborations
NSTX Team