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|a (TOE)ost10133260
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|a (TOE)10133260
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|a E 1.99:ucrl-id--116271
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|a E 1.99:ucrl-id--116271
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|a First-wall heat-flux measurements during ELMing H-mode plasma
|h [electronic resource]
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| 260 |
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|a Washington, D.C. :
|b United States. Dept. of Energy ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
|c 1994.
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| 300 |
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|a 22 p. :
|b digital, PDF file.
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| 336 |
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|a text
|b txt
|2 rdacontent.
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| 337 |
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|a computer
|b c
|2 rdamedia.
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|a online resource
|b cr
|2 rdacarrier.
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|a Published through the Information Bridge: DOE Scientific and Technical Information.
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|a 01/28/1994.
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|a "ucrl-id--116271"
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|a "DE94008310"
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| 500 |
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|a "35AT05000/35AT10020"
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|a Allen, S.L.; Hill, D.N.; Leonard, A.W.; Petrie, T.W.; Lasnier, C.J.
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| 513 |
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|a Topical;
|b 01/01/1994.
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|a In this report we present measurements of the diverter heat flux in DIII-D for ELMing H-mode and radiative diverter conditions. In previous work we have examined heat flux profiles in lower single-null diverted plasmas and measured the scaling of the peak heat flux with plasma current and beam power. One problem with those results was our lack of good power accounting. This situation has been improved to better than 80--90% accountability with the installation of new bolometer arrays, and the operation of the entire complement of 5 Infrared (IR) TV cameras using the DAPS (Digitizing Automated Processing System) video processing system for rapid inter-shot data analysis. We also have expanded the scope of our measurements to include a wider variety of plasma shapes (e.g., double-null diverters (DND), long and short single-null diverters (SND), and inside-limited plasmas), as well as more diverse discharge conditions. Double-null discharges are of particular interest because that shape has proven to yield the highest confinement (VH-mode) and beta of all DIII-D plasmas, so any future diverter modifications for DIII-D will have to support DND operation. In addition, the proposed TPX tokamak is being designed for double-null operation, and information on the magnitude and distribution of diverter heat flux is needed to support the engineering effort on that project. So far, we have measured the DND power sharing at the target plates and made preliminary tests of heat flux reduction by gas injection.
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| 536 |
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|b W-7405-ENG-48.
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| 536 |
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|b AC03-84ER51044.
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|a Heat Flux.
|2 local.
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| 650 |
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7 |
|a Edge Localized Modes.
|2 local.
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| 650 |
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|a H-mode Plasma Confinement.
|2 local.
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| 650 |
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|a Plasma Diagnostics.
|2 local.
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| 650 |
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|a Doublet-3 Device.
|2 local.
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| 650 |
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7 |
|a First Wall.
|2 local.
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| 650 |
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|a Divertors.
|2 local.
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| 650 |
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|a Plasma Physics And Fusion Technology.
|2 edbsc.
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| 710 |
2 |
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|a Lawrence Livermore National Laboratory.
|4 res.
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| 710 |
2 |
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|a General Atomic Company.
|4 res.
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| 710 |
1 |
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|a United States.
|b Department of Energy.
|4 spn.
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| 710 |
1 |
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|a United States.
|b Department of Energy.
|b Office of Scientific and Technical Information.
|4 dst.
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| 856 |
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|u http://www.osti.gov/servlets/purl/10133260-9uGtkr/native/
|z Online Access
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| 907 |
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|a .b59459116
|b 03-06-23
|c 05-25-10
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| 998 |
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|a web
|b 05-25-10
|c f
|d m
|e p
|f eng
|g dcu
|h 0
|i 1
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|s 28c3c47a-911b-50f6-8ee7-97fb2818c9ef
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| 952 |
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|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99:ucrl-id--116271
|h Superintendent of Documents classification
|i web
|n 1
|
