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 573K, 553K and 523K. The effect of enhancement of hydrogenating rates is quantitatively determined.
All Science Journal Classification (ASJC) codes
- Civil and Structural Engineering
- Nuclear Energy and Engineering
- Materials Science(all)
- Mechanical Engineering