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Tritium and Deuterium Retention in Graphite Limiters in TEXTOR

T. Tanabe, K. Miyasaka, M. Rubel, V. Philipps

Fusion Science and Technology / Volume 41 / Number 3P2 / May 2002 / Pages 924-928

Material Interaction and Permeation / Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001

In order to investigate tritium behavior in tokamak, we have measured surface distributions of deuterium and tritium on graphite limiter tiles used in TEXTOR under D-D operation by means of an ion beam analysis and tritium imaging plate technique, respectively. It was found that both distributions were quite different, i.e. deuterium retention was higher at the deposited area, whereas tritium retention was higher at the erosion dominated area. This is because tritium produced by the D-D reaction, initially having 1 MeV, did not fully lose its energy in the TEXTOR plasma and implanted into the plasma facing materials nearly homogeneously, whereas deuterium was codeposited with carbon and boron, the main impurities in the TEXTOR plasma. This is also confirmed by the finding that high level of tritium was detected beneath the deposited layer. Tritium distribution, however, was modified by the temperature increase due to plasma heat load. Thus the comparison of tritium profiles with the deuterium profile gives a large amount of important and new information on PMI, and may be used as a new diagnostic technique for PMI.

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