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 573K, 553K and 523K. The effect of enhancement of hydrogenating rates is quantitatively determined.
Original language | English |
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Pages (from-to) | 1484-1487 |
Number of pages | 4 |
Journal | Fusion Engineering and Design |
Volume | 85 |
Issue number | 7-9 |
DOIs | |
Publication status | Published - Dec 2010 |
All Science Journal Classification (ASJC) codes
- Civil and Structural Engineering
- Nuclear Energy and Engineering
- Materials Science(all)
- Mechanical Engineering