| 摘要 |
A method for production of a fuel cladding tube for a nuclear reactor, characterized by the preparation of an ingot of an alloy of zirconium with the following composition by weight %: 0.8%≦̸Nb≦̸2.8%, traces≦̸Sn≦̸0.65%, 0.015%≦̸Fe≦̸0.40%, C≦̸100 ppm, 600 ppm≦̸O≦̸2300 ppm, 5 ppm≦̸S≦̸100 ppm, Cr+V≦̸0.25%, Hf≦̸75 ppm and F≦̸1 ppm the remainder being zirconium and impurities arising from production. The ingot is then subjected to forging, a hardening and thermomoechanical treatments comprising cold laminations separated by intermediate annealing, all intermediate annealings being carried out at a temperature below the α→α+&bgr; transition temperature of the alloy, finishing with a recrystallization annealing and resulting in the production of a tube, whereupon an optional external cleaning of the tube is carried out and a mechanical polishing of the external surface of the tube is carried out to give a roughness Ra less than or equal to 0.5 μm. The invention further relates to a fuel cladding tube obtained thereby. |
