| 摘要 |
In the manufacture of cladding tubes of a zirconium-based alloy for fuel rods for nuclear reactors by extrusion of the zirconium-based alloy and cold rollings of the extruded product with annealings, intermediate annealings, between the cold rollings and a beta -quenching of the extruded product prior to the last cold rolling, a cladding tube is provided which has at the same time good corrosion properties and mechanical properties by performing the beta -quenching prior to a cold rolling, after which an intermediate annealing is performed at a temperature of 500 DEG -675 DEG C., and preferably at a temperature of 500 DEG -610 DEG C. The zirconium-based alloy is a zirconium-tin alloy comprising 1.2-1.7% tin, 0.07-0.24% iron, 0.05-0.15% chromium and 0-0.08% nickel. |
