The DIII-D summary contribution to the final INTOR workshop

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In SIII-D, good H-mode confinement has been obtained with up to 6 MW of neutral-beam injection (NBI). In this report we summarize the essential features of divertor operation for DIII-D H-mode plasma. Briefly, our measurements show that: Large edge density and temperarture gradients are obtained with scale lengths of a few cm at the midplane; In the steady state, approximately 10-20% of the input power is deposited on the divertor plates in a region that is peaked on the separatrix and extends radially over )approx equal) 2-4 cm at the outboard intercept. More power (2:1) reaches the outboard intercept than ... continued below

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Pages: 21

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Hill, D. N.; Allen, S. L.; Brooks, N. H.; Content, D.; DeBoo, J. C.; Gohil, P. et al. February 26, 1988.

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Description

In SIII-D, good H-mode confinement has been obtained with up to 6 MW of neutral-beam injection (NBI). In this report we summarize the essential features of divertor operation for DIII-D H-mode plasma. Briefly, our measurements show that: Large edge density and temperarture gradients are obtained with scale lengths of a few cm at the midplane; In the steady state, approximately 10-20% of the input power is deposited on the divertor plates in a region that is peaked on the separatrix and extends radially over )approx equal) 2-4 cm at the outboard intercept. More power (2:1) reaches the outboard intercept than the inboard; Low electron temperature (less than or equal to20eV) and high density (n/sub e//sup div/ )approx equal) n/sub e//sup main/ greater than or equal to 3-10 )times)10/sup 19/ m/sup -3/ at the divertor plates indicate that DIII-D obtains a high-recycling divertor during H-mode. DEGAS neutral transport modeling is consistent with these results; The duration of good H-mode confinement is limited by Edge Localized Modes (ELMs) rather than increasing impurity radiation; The dominant impurities, C and Ni are concentrated in the edge plasma (ra greater than or equal to 0.5) for I/sub p/ greater than or equal to 1 MA; and Global impurity concentrations fall markedly with increasing plasma current. The remainder of this report contains a brief description of the DIII-D tokamak and the relavant diagnostics, a summary of the divertor plasma parameters obtained during the H-mode and the heat loads on the diverotr target plates. The results of measurements of the central radiation and impurity content using data from an EUV spectrometer and a 21 channel bolometer array are discussed, and finally a discussion of the implication of these results for the CIT and ITER tokamak designs is given. 8 refs., 8 figs

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Pages: 21

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NTIS, PC A; 03/MF A01.

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  • Other: DE88008021
  • Report No.: UCID-21329
  • Grant Number: W-7405-ENG-48
  • DOI: 10.2172/5181705 | External Link
  • Office of Scientific & Technical Information Report Number: 5181705
  • Archival Resource Key: ark:/67531/metadc1060015

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  • February 26, 1988

Added to The UNT Digital Library

  • Jan. 22, 2018, 7:23 a.m.

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  • March 20, 2018, 1:47 p.m.

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Hill, D. N.; Allen, S. L.; Brooks, N. H.; Content, D.; DeBoo, J. C.; Gohil, P. et al. The DIII-D summary contribution to the final INTOR workshop, report, February 26, 1988; California. (digital.library.unt.edu/ark:/67531/metadc1060015/: accessed August 16, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.