Tritium profile in plasma-facing components following D-D operation

K. Sugiyama, T. Tanabe, K. Miyasaka, K. Masaki, K. Tobita, N. Miya, V. Philipps, M. Rubel, C. H. Skinner, C. A. Gentile, T. Saze, K. Nishizawa

Research output: Contribution to journalConference articlepeer-review

16 Citations (Scopus)


We have investigated the tritium depth profile near the surface of the limiter/divertor tiles used in the deuterium fueled machines, such as TEXTOR, TFTR and JT-60U by means of the imaging plate technique and a tritium survey monitor. Tritium depth profiles near the surface of the sample tiles were estimated by comparing the experimental results to a calculation using a 3-D Monte-Carlo code. In every sample tile, there was little tritium in the range from the surface to 1 μm depth. In contrast, tritium density tended to increase beyond 1 μm depth. These results indicate that the tritium retained near the surface was easily removed by isotope exchange with a deuterium plasma or various other tritium removal operations. On the other hand, such operations did not remove tritium retained beyond 1 μm depth, and this could be a potential issue in a next D-T machine.

Original languageEnglish
Pages (from-to)874-879
Number of pages6
JournalJournal of Nuclear Materials
Issue number1-3 PART A
Publication statusPublished - 2004 Aug 1
EventProceedings of the 11th Conference on Fusion Research - Kyoto, Japan
Duration: 2003 Dec 72003 Dec 12


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