Reassessment of tritium content in CFC tiles exposed to the JET D-T campaign in 1997

Jari Likonen (Corresponding Author), N. Bekris, J.P. Coad, C. Ayres, N. Gotts, I. Jepu, Y. Zayachuk, A. Widdowson, I. Wilson, N. Catarino, E. De alves

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In 2019 two MkIIA divertor tiles (6IN3 and 4BN4) exposed during DTE1 were retrieved at CCFE for Thermal Desorption Spectroscopy (TDS) and pyrolysis analyses. A set of samples were prepared using a coring technique. The highest tritium (T) inventories were found in the shadowed corner of the inner divertor due to asymmetric deposition. TDS analyses indicated that T is desorbed at rather high temperatures with maximum release peaks at ∼590 and 820 °C. A few samples were reannealed at 850 °C using the same heating procedure and it turned out that a further ∼40–50 % of T was still released indicating that the annealing procedure used does not empty the sample completely. Pyrolysis results for thin disks cut from the surface of the tile were somewhat higher than the corresponding TDS results. T amounts were also investigated as a function of depth from the tile surface up to a depth of ∼4.5 mm and T was detected at these depths. Comparison was also made with old results obtained with the pyrolysis technique and a PIN-diode method a few years after the DTE1 experiment, allowing for the natural decay and off-gassing of T. Our results agree within a factor of ∼3 with these results.

Original languageEnglish
Article number101312
JournalNuclear Materials and Energy
Publication statusPublished - Oct 2022
MoE publication typeA1 Journal article-refereed


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