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Preparation of the liquid lithium divertor plates for NSTX

  • R. E. Nygren
  • , G. R. McKee
  • , J. A. Fordham
  • , S. A. Lewis
  • , H. Kugel
  • , R. A. Ellis
  • , M. E. Viola
  • , J. S. O'Dell

Research output: Contribution to journalArticlepeer-review

Abstract

Each of the four toroidal panels of the liquid lithium divertor being installed in NSTX for operation in the 2010 campaign is a conical section inclined at 22° like the previous graphite divertor tiles. Each panel is a copper plate clad with stainless steel and a surface layer of porous plasma sprayed molybdenum (Mo) that will host lithium deposited from an evaporator. This paper describes the processes in fabrication; these include cutting to rough shape, die pressing into conical sections, machining to near final shape with holes for electrical heaters, thermocouples and a groove for a cooling tube, brazing of the 0.25-mm cladding and vacuum plasma spraying of the Mo coating.

Original languageEnglish (US)
Pages (from-to)592-596
Number of pages5
JournalJournal of Nuclear Materials
Volume417
Issue number1-3
DOIs
StatePublished - Oct 1 2011

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • General Materials Science
  • Nuclear Energy and Engineering

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