Abstract:
A process for the manufacture of a flat product of zirconium alloy having a width between 50 and 600 mm from a flat cold rolled product. The cold rolled product is heated to the beta range and maintained in the beta range using an infra-red heating device with a wavelength of between 0.8 and 5 microns, the maximum temperature difference over the width of the product being less than 35.degree. C. The product is then rapidly cooled and optionally annealed to obtain a flat product, which can be a strip, sheet or band.
Abstract:
A method for fabricating a composite cladding comprised of a moderate-purity metal barrier of zirconium metallurgically bonded on the inside surface of a zirconium alloy tube which improves corrosion resistance. The improved corrosion resistance of the liner is accomplished by suitable heat treatment of the Zircaloy-zirconium composite cladding to allow diffusion of alloying elements, notably Fe and Ni, from the Zircaloy into the zirconium, in particular, to the inner surface of the zirconium liner. This diffusion anneal reduces the undesirable tendency of zirconium liner to oxidize rapidly.
Abstract:
A method of increasing intergranular stress corrosion cracking resistance of Alloy 718 in water reactor environments is described where the alloy is heat treated at a high solution annealing temperature to dissolve grain boundary precipitates formed during thermomechanical processing. A water quenching step is advantageously employed following the high solution annealing. The alloy is then aged at two separate temperatures and finally air cooled to room temperature.
Abstract:
A zirconium based alloy plate of low irradiation growth, containing not more than 5 wt % Sn and/or not more 5 wt % Nb, and the balance Zr of not less than 90 wt %. The alloy plate has a texture that orientation (Fr value) with respect to direction perpendicular to the surface of the plate ranges from 0.20 to 0.50. This alloy plate is effective in being used to form a fuel channel box. Also a fuel assembly using this channel box is provided in which the crystal orientation of the zirconium alloy is made random by a heat treatment. Specifically, by the heat treatment, the Fr, Ft, and Fl values thereof are set to 0.25 to 0.50, 0.25 to 0.36, and 0.25 to 0.36, respectively.
Abstract:
The invention relates to a method of making tubes of Zirconium alloys containing 1-5 percent by weight of alloying elements such as Sn, Fe, Cr and Ni. According to the invention an improved corrosion resistance can be reached by means of annealing after extrusion and between cold rollings within a well defined temperature range in the .alpha.-phase zone during considerably longer times than standardized for the purpose of reaching equilibrium between secondary phase particles and Zirconium matrix and in that way a minimum content of Fe in solid solution.
Abstract:
A process for improving resistance of control rod guide tube split pins in nuclear reactors to stress corrosion cracking comprising heating the split pin to a critical elevated temperature level, cooling at least the surface portions of the split subject to stress corrosion cracking and then permitting the split pin to come to ambient temperature.
Abstract:
A method for coating a nuclear fuel with a burnable poison and a burnable poison coated nuclear fuel made by the method. The nuclear fuel is surface cleaned, and then a burnable poison layer is sputtered thereon. A sputtering deposition rate is picked that preferably will heat the nuclear fuel surface between 200.degree. C. and 600.degree. C. For deposition rates that result in heating the nuclear fuel surface to less than 200.degree. C., external heat is applied to heat the nuclear fuel surface between 200.degree. C. and 600.degree. C. To make the burnable poison layer less hygroscopic, an overcoat layer of a hydrophobic material is sputtered on the burnable poison layer.
Abstract:
A method of manufacturing a nuclear fuel or poison which includes heating particulate nuclear fuel or poison to between about 800* C. and 1400* C., contacting the heated material with an acetylene containing atmosphere having an acetylene partial pressure of at least about 0.65 atmosphere to deposit a spongy pyrolytic carbon coating on the particles followed by depositing a dense exterior fission products retentive coating on the spongy carbon coating.
Abstract:
A zirconium alloy suitable for forming reactor components that exhibit reduced irradiation growth and improved corrosion resistance during operation of a light water reactor (LWR), for example, a boiling water reactor (BWR). During operation of the reactor, the reactor components will be exposed to a strong, and frequently asymmetrical, radiation fields sufficient to induce or accelerate corrosion of the irradiated alloy surfaces within the reactor core. Reactor components fabricated from the disclosed zirconium alloy will also tend to exhibit an improved tolerance for cold-working during fabrication of the component, thereby simplifying the fabrication of such components by reducing or eliminating subsequent thermal processing, for example, anneals, without unduly degrading the performance of the finished component.