Title of article :
Verification to recover tritium in neutron-irradiated Li by Y plate
Author/Authors :
Fukada، نويسنده , , Satoshi and Maeda، نويسنده , , Yasushi and Kinoshita، نويسنده , , Mika and Muroga، نويسنده , , Takeo، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2007
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.
Keywords :
tritium , Recovery , HTO , HT , HF treatment , Yttrium , lithium
Journal title :
Fusion Engineering and Design
Journal title :
Fusion Engineering and Design