Abstract
The recovery of tritium from neutron-irradiated Li by an Y plate was experimentally investigated for tritium removal in a Li loop of IFMIF. The molar fraction of tritium included in neutron-irradiated Li ranges from 0.007 to 0.04 ppm. The Y plate at 400-500 °C successfully recovered the low concentration of tritium dissolved in Li. Although HTO as well as HT remained in Li without T recovery, the main chemical species of tritium remaining in Li after recovery was HT, and HT and HTO was released from Y after T recovery. SEM-EDX analysis revealed the transfer of not only tritium or hydrogen but also oxygen originally included in Li. The treatment of Y by a HF acid solution was effective to remove oxides formed on the Y plate and to enhance its hydrogenating rate.
| Original language | English |
|---|---|
| Pages (from-to) | 2152-2157 |
| Number of pages | 6 |
| Journal | Fusion Engineering and Design |
| Volume | 82 |
| Issue number | 15-24 |
| DOIs | |
| Publication status | Published - Oct 2007 |
All Science Journal Classification (ASJC) codes
- Civil and Structural Engineering
- Nuclear Energy and Engineering
- Materials Science(all)
- Mechanical Engineering