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

4 Scopus citations

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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