Abstract
The International Fusion Materials Irradiation Facility (IFMIF) is designed to provide an intense neutron source for the development of fusion reactor materials. Neutron is supplied by the D– 7Li reaction, and at the same time tritium (T) is generated as its by-product. Therefore, the removal of T generated in Li becomes inevitable. It is proved in the present study that HF pretreatment of Y getter materials leads to enhance hydrogenating rates of Y placed in Li. The ratio of the H removal rate of HF-treated Y to that of non-treated Y is determined under the conditions of three different temperatures of 573 K, 553 K and 523 K. The effect of enhancement of hydrogenating rates is quantitatively determined.
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