A tritium inventory management scheme for BPX

M. Ulrickson, Robert James Goldston, J. N. Brooks, H. F. Dylla, G. H. Neilson, K. L. Wilson

Research output: Chapter in Book/Report/Conference proceedingConference contribution


Operation of the Burning Plasma Experiment (BPX) with a deuterium-tritium plasma and graphite divertor plates will result in significant retention of tritium in layers of eroded and subsequently redeposited carbon. This trapped tritium is at risk of release during a vacuum accident. An administrative limit of 2 g of releasable tritium has been established for assessment of the environmental impact of such an event. Analysis of the erosion and redeposition process indicates that the 2-g limit will be reached in about 200 full-parameter discharges. Helium-oxygen glow discharge cleaning will be used to remove the redeposited carbon and the trapped tritium. It is calculated that about 90 h of cleaning are required to remove the trapped tritium from 200 plasmas. The cleaning will be done during scheduled maintenance periods every third week. Studies indicate that the tritium inventory can be effectively managed with helium-oxygen glow discharge cleaning.

Original languageEnglish (US)
Title of host publicationProceedings - 14th IEEE/NPSS Symposium Fusion Engineering, FUSION 1991
PublisherInstitute of Electrical and Electronics Engineers Inc.
Number of pages4
ISBN (Electronic)0780301323
StatePublished - 1991
Event14th IEEE/NPSS Symposium Fusion Engineering, FUSION 1991 - San Diego, United States
Duration: Sep 30 1991Oct 3 1991

Publication series

NameProceedings - Symposium on Fusion Engineering


Conference14th IEEE/NPSS Symposium Fusion Engineering, FUSION 1991
Country/TerritoryUnited States
CitySan Diego

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering


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