Abstract: A cladding is provided for use in housing fissionable material in water cooled nuclear fission reactors. The cladding has inner and outer surfaces and includes (1) a cross-section of a Zirconium-based alloyed matrix, and (2) alloying elements in sufficient concentration to form precipitates disposed in the matrix. The cladding includes no more than 20 parts per million nitrogen by weight and is typically a modified Zircaloy-2 or Zircaloy-4. Metallurgically bonded to the inner region of the cladding is a zirconium barrier layer.

Abstract: A reference electrode is disclosed, comprised of a ceramic housing comprised of a bottom and a sidewall means extending from the bottom to a cylindrical housing top to define an inner channel. The channel contains a silver electrode extending therefrom and a deposit of a silver salt. The housing having a bore substantially radial to the axis of the housing extending through oppositely facing sidewall means, and a ceramic rod configured to fit in the bore and form a friction bond is positioned in the bore to form an annular junction that permits transfer of ions across the junction. Means for electrically isolating the silver electrode are mounted on the housing top.

Abstract: A method for annealing a Zircaloy member having a cold worked or beta quenched crystal structure to mitigate the reduction in nodular corrosion resistance caused by the anneal comprises, annealing the member in an atmosphere comprising oxygen and the balance an inert atmosphere to form an adherent black oxide on the member.

Abstract: A container for electrochemical reactants for an electrode is provided, as well as electrodes employing the same. The electrodes can withstand the rigorous environment of a nuclear reactor core. The design of the container reduces stresses in the electrode and significantly improves its reliability. The container has a generally cylindrical member of an insulator. The member has a base region with a cut-out extending therethrough. Sidewall means extend from the base to define a cavity for containing electrochemical reactants, e.g., silver chloride. An insert of an insulator at one end mates with the cut-out and at another end mates with and is brazed to a cap for the container. The insert has a second sidewall means for holding the electrochemical reactants, and is shaped to fit within the first sidewall means. The base of the insert and the the cut-out are metallized for acceptance of a silver base.

Abstract: A container for electrochemical reactants for an electrode is provided, as well as electrodes employing the same. The electrodes can withstand the rigorous environment of a nuclear reactor core. The design of the container reduces stresses in the electrode and significantly improves its reliability. The container has a generally cylindrical member of an insulator. The member has a base region whose outer surface is a surface attachment region. The base region has an annular channel for a lead. The base region also has a generally conical cut-out. Sidewall means extend from said base to define a cavity for containing electrochemical reactants, e.g., silver chloride. A generally conical insert of an insulator mates with the cut-out. The outer surface of the insert, cut-out, and surface attachment region is metallized, and the insert is set in place by brazing. In the electrode the lead is in electrical contact with the apex of the insert.

Abstract: Zirconium-based corrosion resistant alloys for use primarily as a cladding material for fuel rods in a boiling water nuclear reactor consist essentially of by weight percent about 0.5 to 2.0 percent tin, about 0.24 to 0.40 percent of a solute composed of copper, nickel and iron, wherein the copper is at least 0.05 percent, and the balance zirconium. Nuclear fuel elements for use in the core of a nuclear reactor have improved corrosion resistant cladding made from these zirconium alloys or composite claddings have a surface layer of the corrosion resistant zirconium alloys metallurgically bonded to the outside surface of a Zircaloy alloy tube. The claddings may contain an inner barrier layer of moderate purity zirconium metallurgically bonded on the inside surface of the cladding to provide protection from fission products and gaseous impurities generated by the enclosed nuclear fuel.

Abstract: A nuclear fuel element for use in the core of a nuclear reactor is disclosed having an improved corrosion resistant cladding. The cladding is comprised of zirconium alloys containing in weight percent 0.5 to 2.0 percent tin, or 0.5 to 2.5 percent bismuth, or 0.5 to 2.5 percent bismuth and tin, and about 0.5 to 1.0 percent of a solute composed of a member selected from the group consisting of molybdenum, niobium, tellurium and mixtures thereof, and the balance zirconium. Composite claddings are disclosed having a surface layer of one of the corrosion resistant zirconium alloys metallurgically bonded to a Zircaloy alloy tube. Claddings may contain an inner barrier layer of a moderate purity zirconium metallurgically bonded on the inside surface of the cladding to provide protection from fission products and gaseous impurities generated by the enclosed nuclear fuel.

Abstract: A nuclear fuel element for use in the core of a nuclear reactor is disclosed having an improved corrosion resistant cladding. The cladding is comprised of zirconium alloys containing in weight percent 0.5 to 2.0 percent tin, or 0.5 to 2.5 percent bismuth, or 0.5 to 2.5 percent bismuth and tin, and about 0.5 to 1.0 percent of a solute composed of a member selected from the group consisting of molybdenum, niobium, tellurium and mixtures thereof, and the balance zirconium. Composite claddings are disclosed having a surface layer of one of the corrosion resistant zirconium alloys metallurgically bonded to a Zircaloy alloy tube. Claddings may contain an inner barrier layer of a moderate purity zirconium metallurgically bonded on the inside surface of the cladding to provide protection from fission products and gaseous impurities generated by the enclosed nuclear fuel.

Abstract: A conductivity probe able to withstand high water temperatures and pressures, and intense nuclear radiation is suitable for use within the core of the nuclear reactor. The probe is made with a ceramic insulator, such as sapphire, and a central electrode that is mounted on the insulator. A sleeve that supports the insulator and the central electrode is made from metals having a coefficient of thermal expansion compatible with the coefficient of thermal expansion of the insulator, such as Kovar. The central electrode and sleeve are bonded to the insulator by a brazed compressive seal that protects an internal conductor in the probe from intrusion of the reactor water. A counter electrode made from a corrosion resistant metal, such as Kovar, is attached to the sleeve so that it extends over the central electrode a fixed, spaced distance. A positioning and signal transfer arrangement operatively supports the sleeve and conveys electrical signals to and from the two electrodes.

Abstract: Zirconium-based corrosion resistant alloys for use primarily as a cladding material for fuel rods in a boiling water nuclear reactor consist essentially of by weight percent about 0.5 to 2.0 percent thin, about 0.24 to 0.40 percent of a solute composed of copper, nickel and iron, wherein the copper is at least 0.05 percent, and the balance zirconium. Nuclear fuel elements for use in the core of a nuclear reactor have improved corrosion resistant cladding made from these zirconium alloys or composite claddings have a surface layer of the corrosion resistant zirconium alloys metallurgically bonded to the outside surface of a Zircaloy alloy tube. The claddings may contain an inner barrier layer of moderate purity zirconium metallurigcally bonded on the inside surface of the cladding to procide protection from fission products and gaseous impurities generated by the enclosed nuclear fuel.

Abstract: Zirconium-based corrosion resistant alloys for use primarily as a cladding material for fuel rods in a boiling water nuclear reactor which consist essentially of 0.5 to 2.5 weight percent bismuth, or alternatively, 0.5 to 2.5 weight percent of a mixture of tin and bismuth, 0.5-1.0 weight percent of a solute composed of a member selected from the group consisting of niobium, molybdenum, tellurium, and mixture thereof, alternatively, the solute will be composed of tellurium and will be in the range of 0.3-1.0 weight percent, and the balance being zirconium.

Abstract: Zirconium-based corrosion resistant alloys are provided primarily for use as a cladding material for fuel rods in a boiling water nuclear reactor, the alloy in one embodiment consisting essentially of about 0.5-2.0 percent by weight of tin, about 0.5-1.0 percent by weight of a solute, the solute being composed of a member selected from the group consisting of molybdenum, tellurium and mixtures thereof, or alternatively, the solute will contain niobium in combination with molybdenum and/or tellurium and the remainder being zirconium, and in another embodiment the alloy consists essentially of about 0.5-2.0 percent by weight of tin 0.3-1.4 percent by weight of a solute, the solute being composed of tellurium, and the remainder being zirconium.

Abstract: A sintered metallic oxide article is disclosed comprising a non-porous body having at least one porous region formed therein in the general shape of a hollow cylinder, said region placing opposite sides of the body in flow communication. A method is set forth for producing the porous region with a preselected effective open cross-sectional area.

Abstract: A sintered metallic oxide article is disclosed comprising a non-porous body having at least one porous region formed therein in the general shape of a hollow cylinder, said region placing opposite sides of the body in flow communication. A method is set forth for producing the porous region with a preselected effective open cross-sectional area.

Abstract: An electrochemical apparatus and a testing procedure are described for predicting the susceptibility of certain zirconium-base alloys to nodular corrosion in boiling water reactor environments. A chemically polished pre-determined area of the surface of the zirconium-base alloy is made the anode in an electrochemical cell. A constant direct current (d-c) having an alternating current (a-c) superimposed thereon is applied to the cell and the quadrature component of the a-c cell voltage is monitored in order to measure the value of the depth of the minimum occurring in the quadrature component of the a-c cell voltage-versus-time relationship after a d-c cell voltage of at least eight volts has been reached. The application of a-c to the cell is stopped and the constant d-c previously applied is decreased by a a step-change to a constant value providing a reduction of at least one-half in the current density.

Abstract: A state of charge gauge for measuring the state of charge of secondary batteries, such as the type employed in electric vehicles, includes a microprocessor which, when supplied with data varying in accordance with battery discharge current and battery terminal voltage, determines battery resistance. Having determined battery resistance which is a dynamically varying parameter dependent on battery temperature and age, the microprocessor computes the total battery charge capacity. Comparison of the quantity of battery charge already depleted with the previously computed total battery charge capacity yields an accurate indication of remaining battery charge.