Experimental investigation of tritium release behavior from neutron irradiated LiAlO2 with Zr for tritium production in a high-temperature gas-cooled reactor

Abstract

Tritium production using nuclear reactions of neutrons with lithium in a high temperature gas-cooled reactors has been studied as an external source of fuel tritium in the early stage of fusion reactor operation. In order to control tritium migration throughout the reactor, it is important to understand tritium release behaviors from Zr-containing LiAlO₂, which are used as tritium producing materials. In this study, tritium release behavior from neutron irradiated LiAlO₂ with and without Zr ware investigated by heating to 900 °C. In the case of heating only LiAlO₂, most tritium was released in the chemical form of HTO. On the other hand, in the case of heating Zr-containing LiAlO₂, the chemical form of tritium was mostly HT. This result indicates that even if tritium is released from LiAlO₂ as HTO, it is effectively absorbed by Zr at 900 °C.