Abstract: A zirconium alloy that is resistant to shadow corrosion for a boiling water nuclear reactor fuel assembly component, the alloy being characterized in that: its composition in percentages by weight is as follows: Nb=0.4%-4.5% Sn=0.20%-1.7% Fe=0.05%-0.45% Fe+Cr+Ni+V=0.05%-0.45%, with Nb?9×[0.5?(Fe+Cr+V+Ni)] S=traces-400 ppm C=traces-200 ppm Si=traces-120 ppm O=600 ppm-1800 ppm the balance being Zr and impurities from processing; in that, during fabrication, after its last hot deformation, it is subjected to one or more heat treatments lying in the range 450° C. to 610° C. for a total duration of at least 4 h, with at least one cold rolling operation with a rolling ratio of at least 25%; and in that a final heat treatment operation is performed at a temperature in the range 450° C. to 610° C. for 1 minute to 20 hours. A fuel assembly component made of the alloy, a fuel assembly including the component, and the use thereof.

Abstract: A method for design of a fuel assembly for nuclear reactors, including structural components made from zirconium alloy: the mean uniaxial tensile or compressive stress to which the components are subjected during the assembly life is calculated, the zirconium alloy of which the components are made is selected according to the following criteria: those components subjected to an axial or transverse compressive stress of between ?10 et ?20 MPa are made from an alloy with a content of Sn between Sn=(=0.025??0.25)% and Sn=?0.05?%: those components subjected to such a stress of between 0 et ?10 MPa are made from an alloy the Sn content of which is between Sn=traces and Sn=(0.05?+1)%: those components subjected to such a stress of between 0 and +10 MPa are made from an alloy the Sn content of which is between Sn=0.05% and Sn=(0.07?+1)%: and those components subjected to such a stress of between +10 and +20 MPa are made from an alloy the content of SN of which is between 0.05% and 1.70%.

Abstract: 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 ???+? 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 ?m. The invention further relates to a fuel cladding tube obtained thereby.

Abstract: A zirconium alloy that is resistant to shadow corrosion for a boiling water nuclear reactor fuel assembly component, the alloy being characterized in that: its composition in percentages by weight is as follows: Nb=0.4%-4.5% Sn=0.20%-1.7% Fe=0.05%-0.45% Fe+Cr+Ni+V=0.05%-0.45%, with Nb?9×[0.5?(Fe+Cr+V+Ni)] S=traces-400 ppm C=traces-200 ppm Si=traces-120 ppm O=600 ppm-1800 ppm the balance being Zr and impurities from processing; in that, during fabrication, after its last hot deformation, it is subjected to one or more heat treatments lying in the range 450° C. to 610° C. for a total duration of at least 4 h, with at least one cold rolling operation with a rolling ratio of at least 25%; and in that a final heat treatment operation is performed at a temperature in the range 450° C. to 610° C. for 1 minute to 20 hours. A fuel assembly component made of the alloy, a fuel assembly including the component, and the use thereof.

Abstract: A method for design of a fuel assembly for nuclear reactors, including structural components made from zirconium alloy: the mean uniaxial tensile or compressive stress to which the components are subjected during the assembly life is calculated, the zirconium alloy of which the components are made is selected according to the following criteria: those components subjected to an axial or transverse compressive stress of between ?10 et ?20 MPa are made from an alloy with a content of Sn between Sn=(=0.025??0.25)% and Sn=?0.05?%: those components subjected to such a stress of between 0 et ?10 MPa are made from an alloy the Sn content of which is between Sn=traces and Sn=(0.05?+1)%: those components subjected to such a stress of between 0 and +10 MPa are made from an alloy the Sn content of which is between Sn=0.05% and Sn=(0.07?+1)%: and those components subjected to such a stress of between +10 and +20 MPa are made from an alloy the content of SN of which is between 0.05% and 1.70%.

Abstract: A method for production of a fuel cladding tube for a nuclear reactor, characterised 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 ???+? transition temperature of the alloy, finishing with a recrystallisation 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 ?m. The invention further relates to a fuel cladding tube obtained thereby.

Abstract: The alloy has a base composition similar to that of a zirconium alloy of known type used for the manufacture of an element intended for use in the core of a nuclear reactor, such as a cladding tube, a guide tube, or another structural element of a fuel assembly. In addition, the alloy contains sulphur in a proportion by weight of between 8 and 100 ppm and preferably between 8 and 30 ppm.