Tritium recovery from the TFTR vessel

A. Nagy, E. Amerescu, W. Blanchard, R. Camp, M. Casey, K. Chase, M. Cropper, T. Czeizinger, M. DiMattia, C. Gentile, J. Gething, M. Gibson, J. Langford, J. Hosea, D. Hyatt, al et al

Research output: Contribution to conferencePaperpeer-review

3 Scopus citations

Abstract

The Tokamak Fusion Test Reactor (TFTR) was supplied over 7.5×105 Curies combined through the vacuum vessel and Neutral Beam (NB) tritium gas injectors. TFTR has had two short term outages during DT operations plus the final shutdown after DT operations in which tritium held up in the vessel and NB's has been actively recovered. An ion chamber was used to measure the tritium accumulated in the Gas Holding Tanks (GHT) from the vessel throughout all the active and passive processes. The ion chamber compensation for varying gas mixtures was found to be critical in accurate measurement of this recovery.

Original languageEnglish (US)
Pages317-320
Number of pages4
StatePublished - 1998
EventProceedings of the 1997 17th IEEE/NPSS Symposium on Fusion Engineering. Part 1 (of 2) - San Diego, CA, USA
Duration: Oct 6 1997Oct 10 1997

Other

OtherProceedings of the 1997 17th IEEE/NPSS Symposium on Fusion Engineering. Part 1 (of 2)
CitySan Diego, CA, USA
Period10/6/9710/10/97

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

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