Method of manufacturing a fuel cladding tube for a nuclear...

Induced nuclear reactions: processes – systems – and elements – Fuel component structure

Reexamination Certificate

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C376S457000, C148S672000, C148S421000, C420S422000

Reexamination Certificate

active

07738620

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 α→α+β 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.

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PCT International Search Report PCT/FR2005/001844, mailed Nov. 28, 2005.
Isobe et al., “Development of Highly Corrosion Resistant Zirconium-Base Alloys”, Zirconium in the Nuclear Industry: Ninth Symposium, No. 1132, 1991, pp. 346-367.
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