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[1L02] Experimental investigation of tritium release behavior from neutron irradiated LiAlO2 with Zr for tritium production in high-temperature gas-cooled reactor
Keywords:Tritium, High temmperature gas-cooled reactor, Tritium behavior
Although it is essential to elucidate tritium release characteristics from LiAlO2 in order to secure initially loaded tritium in fusion reactors, there are few reports on this subject. In this study, tritium release characteristics of neutron-irradiated Zr-doped LiAlO2 were investigated and the issues of tritium production in actual HTGR were discussed.
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