Abstract:
A method of manufacturing components made of zirconium-based alloy by combining heat treatment with thermal sizing. The heat treatment includes heating the component to a temperature which initiates the transformation from a hexagonal close-packed crystallographic phase of uniform texture to a body-centered cubic crystallographic phase and then quenching to a quench temperature at a rate which initiates transformation to a hexagonal close-packed crystallographic phase having a texture factor f.sub.L =0.28-0.38. The thermal sizing includes heating the component to a temperature less than the quench temperature, but sufficient to anneal the component, and then cooling. Preferably, the thermal sizing is performed twice: before and after the heat treatment.
Abstract:
It has been found that modifying standard Zircaloy alloy processing techniques by limiting the working and annealing temperatures utilized after conventional beta treatment results in Zircaloy alloy product having superior high temperature steam corrosion resistance.
Abstract:
A process for forming a boron-containing coating on the internal surface of a zirconium or zirconium alloy hollow tube by heating the internal surface to a temperature of between 200.degree.-450.degree. C. and passing through the tube a mixture of a volatilized boron compound in helium or argon, such that the boron compound decomposes to form an integral boron containing coating on the internal surface.
Abstract:
The invention concerns a method of producing a cladding tube for nuclear fuel for a nuclear pressure water reactor. According to the method, a tube is formed which at least principally consists of a cylindrical tube component (1) of a Zr-based alloy, with a Nb content between 0.5 and 2.4 weight percent. The cladding tube is finally annealed at a temperature and during a time such that said tube component (1) is partly recrystallized but not completely recrystallized. The invention also concerns a cladding tube, a fuel assembly for a pressure water reactor and the use of a cladding tube.
Abstract:
An absorbent pencil of which at least the lower portion contains a neutron absorber consisting of a hafnium metal compound coated with a wear protection layer of oxide or chromium having a thickness of at least 5 mu m.
Abstract:
A fuel box for a nuclear fuel bundle for a boiling water reactor is manufactured by zirconium alloy plates. The plates have a composition such that the material after beta quenching and heat treatment will have a ductile, so-called basketweave structure.
Abstract:
The invention relates to a fuel element for a pressurized-water reactor comprising a number of fuel rods arranged in a square lattice and wherein certain positions in the lattice contain guide tubes for receiving control rods, wherein the fuel element can be used for higher burnup by manufacturing the guide tubes of the element such that their irradiation-induced growth is reduced and their corrosion resistance is increased compared with conventionally manufactured guide tubes. This is achieved by finally heat-treating the guide tubes in two steps, the first step being a beta quenching and the second step a heat treatment in the alpha-phase region.
Abstract:
A method of manufacturing nuclear fuel elements comprising fuel rods whose cladding tubes are provided with an internal liner layer to obtain PCI resistance in the nuclear fuel element comprises carefully choosing parameters for heat treatment of the inner component even from the machining of an ingot of the inner component. The internal layer of zirconium or a zirconium alloy suitable as inner layer in a PCI-resistant cladding is manufactured, from the fabrication of an ingot of the inner component up to the completion of a cladding tube, comprising forging, rolling, extrusion, heat treatment and final heat treatment, in such a way that the temperature in the inner component never exceeds the temperature when an incipient phase transformation to beta phase takes place.
Abstract:
PCT No. PCT/FR96/00137 Sec. 371 Date Jul. 29, 1997 Sec. 102(e) Date Jul. 29, 1997 PCT Filed Jan. 26, 1996 PCT Pub. No. WO96/24140 PCT Pub. Date Aug. 8, 1996A tube of zirconium-based alloy for constituting all or a portion of a cladding or guide tube for a nuclear fuel assembly. The tube is made of an alloy containing, by weight, 1.0-1.7% of tin, 0.55-0.80% of iron, 0.20-0.60% total of chromium and/or vanadium, and 0.10-0.18% of oxygen, with 50-200 ppm of carbon and 50-120 ppm of silicon. The alloy further contains only zirconium and unavoidable impurities, and it is completely recrystallized.