Germanium-bismuth-containing zirconium-niobium alloy for nuclear power station fuel cladding

The invention relates to a zirconium-niobium alloy which can be used as germanium-bismuth-containing structural materials such as pressurized water reactor nuclear power station fuel cladding, a positioning lattice stripe and the like, and belongs to the technical field of zirconium alloy materials. The zirconium alloy consists of the following chemical components in percentage by weight: 0.9%-1.1% of Nb, 0.01%-0.1% of Ge, 0.1%-0.6% of Bi and the balance of Zr, preferably 0.9%-1.1% of Nb, 0.03%-0.08% of Ge and 0.2%-0.4% of Bi. The zirconium alloy has excellent corrosion resistance, which is obviously superior to that of an Zr-1Nb alloy, in 400 DEG C/10.3MPa superheated steam and 360 DEG C/18.6MPa deionized water, is good in processing performance, and can be used as reactor core structural materials such as fuel element cladding, the positioning lattice stripe and the like in a nuclear power station pressurized water reactor.