Abstract
The recovery of tritium, T, from neutron-irradiated Li by a Y plate was experimentally investigated, and a Y hot trap was designed to remove T from a flowing Li target loop of IFMIF. T generated in Li ranging from 0.01 to O.OSppm in molar fraction was successfully removed by a Y plate at 300-500°C. The ratio of recovered T to generated one increased with temperature and immersion time. HT was the main chemical species of T that was released from Li, while HTO was the main one without Y absorption. SEM-EDX analysis revealed the transfer of not only T but also O originally included in Li as an impurity. Treatment of Y by HF was effective to remove oxides formed on the as-received Y plate and enhanced its hydrogenating rate. Conditions of a Y hot trap designed for the flowing Li target loop of IFMIF are given in the present paper.
| Original language | English |
|---|---|
| Pages (from-to) | 117-121 |
| Number of pages | 5 |
| Journal | Fusion Science and Technology |
| Volume | 54 |
| Issue number | 1 |
| DOIs | |
| Publication status | Published - Jan 1 2008 |
All Science Journal Classification (ASJC) codes
- Civil and Structural Engineering
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering
- Materials Science(all)
- Mechanical Engineering