Removal and Control of Tritium in Lithium Target for International Fusion Materials Irradiation Facility (IFMIF)
Fusion Science and Technology / Volume 41 / Number 3P2 / May 2002 / Pages 845-849
Design and Model / Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 / dx.doi.org/10.13182/FST02-A22704
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This paper describes removal and control of tritium of liquid lithium (Li) target for IFMIF. To produce intense neutrons, 40 MeV deuteron beam with a current of 250 mA is injected into a liquid Li flow with a speed of 20 m/s. D-Li reaction produces tritium with a production rate of 7 g/y. Tritium in Li is removed by a hot trap with an yttrium getter and controlled less than 0.65 appm. As an option, a swamping method with a cold trap is investigated.
