Edge plasma modeling of limiter surfaces in a Tokamak divertor configuration

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During the startup phase of a tokamak the plasma configuration may evolve from a limiter to a divertor configuration. Some of the particle and heat flux from the core will be deposited on material surfaces near the separatrix instead of the divertor plates. Examples of such surfaces include the center-post in most tokamaks, baffles near the x-point that create closed divertors, and outboard limiter surfaces. Two-dimensional edge plasma models for tokamak divertor configurations typically give detailed information about the particle and heat fluxes on the divertor plates, but yield little or no information about fluxes on these other localized surfaces ... continued below

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12 p.; Other: FDE: PDF; PL:

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Rensink, M. E. May 11, 1998.

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During the startup phase of a tokamak the plasma configuration may evolve from a limiter to a divertor configuration. Some of the particle and heat flux from the core will be deposited on material surfaces near the separatrix instead of the divertor plates. Examples of such surfaces include the center-post in most tokamaks, baffles near the x-point that create closed divertors, and outboard limiter surfaces. Two-dimensional edge plasma models for tokamak divertor configurations typically give detailed information about the particle and heat fluxes on the divertor plates, but yield little or no information about fluxes on these other localized surfaces near the core plasma. To realistically model the startup phase of a tokamak it is necessary to compute the plasma interaction with both limiter and divertor surfaces. The UEDGE code [l] has been modified to include these limiter surfaces. In this report we present simulation results for an idealized ITER [2] startup configuration with variations in the limiter penetration depth and surface shape.

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12 p.; Other: FDE: PDF; PL:

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OSTI as DE98058606

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  • 13. international conference on plasma surface interactions, San Diego, CA (United States), 18-22 May 1998

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  • Other: DE98058606
  • Report No.: UCRL-JC--130763
  • Report No.: CONF-980560--
  • Grant Number: W-7405-ENG-48
  • Office of Scientific & Technical Information Report Number: 292472
  • Archival Resource Key: ark:/67531/metadc682716

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  • May 11, 1998

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  • July 25, 2015, 2:20 a.m.

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  • Feb. 16, 2016, 6:32 p.m.

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Rensink, M. E. Edge plasma modeling of limiter surfaces in a Tokamak divertor configuration, article, May 11, 1998; California. (digital.library.unt.edu/ark:/67531/metadc682716/: accessed September 26, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.