AbstractAn in-pile functional test of a fusion blanket with lithium containing ceramics as the tritium breeder is planned in Japan Materials Testing Reactor (JMTR). Therefore, the getter is necessary for the recovery of the tritium gas on in-pile functional test. In this study, ZrNi alloys added other elements, i.e. Fe, Co, etc. were selected as a getter. The equilibrium hydrogen pressure of these alloys and breakthrough properties of hydrogen with the particle packed bed were estimated for its application. Resulting of the examination on plateau pressure of the P–C–T, the same plateau pressure as the uranium was obtained in the Zr1Ni0.2Co0.7Fe0.1 and Zr1Ni0.3Co0.5Fe0.2 in which the pressure was about 4×10−4 Pa at 298 K. The absorption band and amount of hydrogen absorption in the packed bed were about 0.7 cm and 170 cm3/g Zr1Ni0.3Co0.5Fe0.2 in 3 cm/s with 9940 ppm H2+Ar gas at 298 K, respectively. From these results, it was obvious that Zr1Ni0.3Co0.5Fe0.2 was the preferable material for the recovery of tritium gas for in-situ irradiation test of fusion blanket.