Tritium Recovery From Carbon Co-deposits: \textit{ex situ} Studies in Preparation for an \textit{in situ} Thermal Oxidation Experiment in DIII-D

POSTER

Abstract

Tritium trapping in carbon co-deposits is potentially a major cause of T retention in ITER. A possible solution is ``thermo-oxidation,'' involving sub-atmospheric molecular O$_{2}$ at 250$^{^{o}}$-350$^{^{o}}$C. Ex situ lab tests (at U. Toronto) of graphite tiles removed from DIII-D have demonstrated the method in principle and generated a comprehensive database on removal rates. Ex situ tests were also performed for special components (e.g., diagnostic mirrors) used in DIII-D to assess potential damage. The next step is in situ demonstration in DIII-D to show that the D (as proxy for T) and C removed from the tiles actually leaves the vessel, that vessel components are not damaged, and that plasma operation can be recovered quickly. Lab results and implications for the in situ test are discussed.

*Work supported by the Natural Sciences and Engineering Research Council of Canada and by US DOE under W-7405-ENG-48, DE-FC02-04ER54698, and DE-FG02-04ER54578.

Authors

  • P.C. Stangeby

    • U. Toronto
  • J.W. Davis

  • A.A. Haasz

  • B.W.N. Fitzpatrick

  • A.G. McLean

    • U. Toronto
  • P.C. Stangeby

    • U. Toronto
  • Y. Mu

    • U. Toronto
  • S.L. Allen

    • LLNL
    • Lawrence Livermore National Laboratory
  • W.P. West

    • General Atomics
    • GA
  • P.L. Taylor

  • K.L. Holtrop

  • A.W. Hyatt

  • R.L. Boivin

    • GA
  • K. Umstadter

    • UCSD