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