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|a (TOE)ost15014728
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|a (TOE)15014728
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|a E 1.99:ucrl-conf-207411
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|a E 1.99:ucrl-conf-207411
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|a ucrl-conf-207411
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|a Far SOL Transport and Main Wall Plasma Interaction in DIII-D
|h [electronic resource]
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| 260 |
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|a Washington, D.C. :
|b United States. Department of Energy. ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
|c 2004.
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| 300 |
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|a PDF-file: 11 pages; size: 0.2 Mbytes.
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|a text
|b txt
|2 rdacontent.
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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 SciTech Connect.
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|a 10/19/2004.
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|a "ucrl-conf-207411"
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|a 45 12 ISSN 0029--5515.
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|a Presented at: 20th IAEA Fusion Energy Conference, Vilamoura, Portugal, Nov 01 - Nov 06, 2004.
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|a Rudakov, D L; Boedo, J A; Moyer, R A; Stangeby, P C; Watkins, J G; Whyte, D G; Zeng, L; Brooks, N H; Doerner, R P; Evans, T E; Fenstermacher, M E; Groth, M; Hollmann, E M; . Krasheninnikov, S I; Lasnier, C J; Leonard, A W; Mahdavi, M A; McKee, G R; McLean, A G; Pigarov, A Y; Wampler, W R; Wang, G; West, W P; Wong, C C.
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|a Far scrape-off layer (SOL) and near-wall plasma parameters in DIII-D depend strongly on the discharge parameters and confinement regime. In L-mode discharges cross-field transport increases with the average discharge density and flattens far SOL profiles, thus increasing plasma-wall contact. In H-mode between edge localized modes (ELMs), plasma-wall contact is generally weaker than in L-mode. During ELMs plasma fluxes to the wall increase to, or above the L-mode levels. Depending on the discharge conditions ELMs are responsible for 30-90% of the ion flux to the outboard chamber wall. Cross-field fluxes in far SOL are dominated by large amplitude intermittent transport events that may propagate all the way to the outer wall and cause sputtering. A Divertor Material Evaluation System (DiMES) probe containing samples of several ITER-relevant materials including carbon, beryllium and tungsten was exposed to a series of upper single null (USN) discharges as a proxy to measure the first wall erosion.
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|b W-7405-ENG-48.
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|a Doublet-3 Device.
|2 local.
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|a First Wall.
|2 local.
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|a Iaea.
|2 local.
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|a Plasma.
|2 local.
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|a Sols.
|2 local.
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|a Edge Localized Modes.
|2 local.
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|a Thermonuclear Reactors.
|2 local.
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|a Transport.
|2 local.
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| 650 |
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|a Plasma Physics And Fusion.
|2 edbsc.
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| 710 |
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|a Lawrence Berkeley National Laboratory.
|4 res.
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| 710 |
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|a United States.
|b Department of Energy.
|4 spn.
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| 710 |
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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/scitech/biblio/15014728
|z Online Access (via OSTI)
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| 907 |
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|a .b70305419
|b 03-09-23
|c 03-31-12
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| 998 |
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|a web
|b 05-20-19
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|e p
|f eng
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|h 0
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|s 48d9a760-fbc4-5a0e-908d-70245a3511a7
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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-conf-207411
|h Superintendent of Documents classification
|i web
|n 1
|
