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

研究成果: Conference article査読

13 被引用数 (Scopus)

抄録

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.

本文言語English
ページ(範囲)874-879
ページ数6
ジャーナルJournal of Nuclear Materials
329-333
1-3 PART A
DOI
出版ステータスPublished - 2004 8 1
外部発表はい
イベントProceedings of the 11th Conference on Fusion Research - Kyoto, Japan
継続期間: 2003 12 72003 12 12

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Materials Science(all)
  • Nuclear Energy and Engineering

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