Divertor erosion study for TPX and implications for steady-state fusion reactors

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A sputtering erosion analysis was performed for the tilted plate divertor design of the proposed TPX tokamak. High temperature ({approximately} 100 eV), non-radiative, steady-state compatible, plasma edge conditions were used as input to the REDEP erosion/redeposition code. For the reference carbon surface the results show a stable erosion profile, i.e., non-runaway self-sputtering, in spite of carbon self-sputtering coefficients that are locally in excess of unity. The resulting net erosion rates are high (peak {approx} 1--2.5 m/burn-yr) but may be acceptable for a low duty factor experimental device such as TPX. Other surface materials were also analyzed, in part to obtain ... continued below

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5 p.

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Brooks, J.N. December 31, 1995.

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Description

A sputtering erosion analysis was performed for the tilted plate divertor design of the proposed TPX tokamak. High temperature ({approximately} 100 eV), non-radiative, steady-state compatible, plasma edge conditions were used as input to the REDEP erosion/redeposition code. For the reference carbon surface the results show a stable erosion profile, i.e., non-runaway self-sputtering, in spite of carbon self-sputtering coefficients that are locally in excess of unity. The resulting net erosion rates are high (peak {approx} 1--2.5 m/burn-yr) but may be acceptable for a low duty factor experimental device such as TPX. Other surface materials were also analyzed, in part to obtain insight for fusion reactor designs using a similar plasma regime. Both medium and high-Z materials are predicted not to work, due to runaway self-sputtering. Beryllium is stable but has erosion rates as high or higher than carbon. A liquid metal lithium surface has stable sputtering with a zero-erosion potential and may thus be an attractive future material choice.

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5 p.

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INIS; OSTI as DE96005526

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  • 16. IEEE/NPSS symposium on fusion engineering, Champaign, IL (United States), 1-5 Oct 1995

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  • Other: DE96005526
  • Report No.: ANL/TD/CP--86511
  • Report No.: CONF-9510239--5
  • Grant Number: W-31109-ENG-38
  • DOI: 10.2172/195722 | External Link
  • Office of Scientific & Technical Information Report Number: 195722
  • Archival Resource Key: ark:/67531/metadc666243

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  • December 31, 1995

Added to The UNT Digital Library

  • June 29, 2015, 9:42 p.m.

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  • Dec. 14, 2015, 4:55 p.m.

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Brooks, J.N. Divertor erosion study for TPX and implications for steady-state fusion reactors, report, December 31, 1995; Illinois. (https://digital.library.unt.edu/ark:/67531/metadc666243/: accessed May 24, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.