Home / Store / Journals / Electronic Articles / Fusion Science and Technology / Volume 60 / Number 4 / Pages 1495-1498
Masashi Shimada, T. Otsuka, R. J. Pawelko, P. Calderoni, J. P. Sharpe
Fusion Science and Technology / Volume 60 / Number 4 / Pages 1495-1498
Format:electronic copy (download)
Tritium retention in plasma-facing components influences the design, operation, and lifetime of fusion devices such as ITER. Most of the retention studies were carried out with the use of either hydrogen or deuterium. Tritium Plasma Experiment is a unique linear plasma device that can handle radioactive fusion fuel of tritium, toxic material of beryllium, and neutron-irradiated material. A tritium depth profiling method up to mm range was developed using a tritium imaging plate and a diamond wire saw. A series of tritium experiments (T2/D2 ratio: 0.2 and 0.5 %) was performed to investigate tritium depth profiling in bulk tungsten, and the results shows that tritium is migrated into bulk tungsten up to mm range.
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