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Tritium Distribution on First Wall Carbon Tiles in JT-60U

M. Yoshida et al.

Fusion Science and Technology / Volume 60 / Number 4 / November 2011 / Pages 1560-1563

Interaction with Materials / Proceedings of the Ninth International Conference on Tritium Science and Technology (Part 2)

T retention and its depth profile in the graphite tiles used for first wall of JT-60U have been measured by a tritium imaging plate technique and a full combustion method. T was found only limited depth beneath the plasma facing surface and little in both the surface region shallow than 1 m and in bulk more than 1mm in depth. Although most of T produced by DD reactions are thermalized and neutralized in plasma and impinge on the plasma facing surface and penetrate into the inner surface, they are isotopically replaced by subsequently incoming D. Only some of high energy T escaping from plasma are directly implanted beneath the surface and retained escaping from the isotopic replacement until attainment of a saturation concentration.

 
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