An in-situ irradiation test of a fusion blanket is planned in JMTR (Japan Materials Testing Reactor) using lithium containing ceramics as the tritium breeder and beryllium as the neutron multiplier. Therefore, it is necessary to develop getters for the recovery of the tritium gas. In this study, Zr9Ni11 alloy was chosen as a getter, and pressure-composition isotherms between 20°C and 300°C, and other properties were measured for its application. The breakthrough test of hydrogen was carried out with Ar+H2 gas. The evaluation of the examined getter materials leads to the conclusion that the Zr9Ni11 alloy may be used for the in-situ irradiation test of fusion blanket.