Abstract: An improved process for the conversion of gaseous uranium hexafluoride to a uranium oxide rich composition in the presence of an active flame in a reaction zone is achieved by introducing a first gaseous reactant comprising a mixture of uranium hexafluoride and an oxygen-containing carrier gas and a second gaseous reactant comprising a reducing gas, the reactants being separated by a shielding gas as introduced to the reaction zone. The shielding gas temporarily separates the gaseous reactants and temporarily prevents substantial mixing and reacting of the gaseous reactants. The flame occurring in the reaction zone is maintained away from contact with the inlet introducing the mixture to the reaction zone.

Abstract: An improved nuclear fuel element is disclosed for use in the core of nuclear reactors. The improved nuclear fuel has a composite cladding container comprising an outer layer having two coatings on the inside surface with the first coating on the outer layer being a diffusion barrier and the second coating on the first coating being a metal layer. The diffusion barrier is comprised of chromium or a chromium alloy, and the metal layer is selected from the group consisting of copper, nickel, iron and alloys thereof. The nuclear fuel element comprises a container of the elongated composite cladding, a central core of a body of nuclear fuel material disposed in and partially filling the container and forming an internal cavity in the container, an enclosure integrally secured and sealed at each end of said container and a nuclear fuel material retaining means positioned in the cavity.

Abstract: A filter unit adapted for receiving a flow of fluid potentially carrying particulate material and for holding filters transverse to the flow is disclosed, and in one preferred application of the invention the flow is an air stream containing radioactive particles. The filter unit has a generally cubic-shaped housing having a fluid inlet opening and a fluid outlet opening in two opposite surfaces and preferably these openings are provided with flanges. The housing is also provided in its lateral surfaces with a first opening and a second opening enabling insertion and removal of filters though these openings. The openings are preferably in the same lateral surface or wall. Each opening has a door means mounted to close the opening with each door means being capable of being opened at least 90.degree. to the lateral surface of the housing on which the door means is mounted.

Abstract: An improved nuclear fuel element is disclosed for use in the core of nuclear reactors. The improved nuclear fuel element has a metal liner and a diffusion barrier disposed between the cladding and the nuclear fuel material. The diffusion barrier is in the form of a metal coating with the diffusion barrier being coated on the internal surface of the cladding in one embodiment and the diffusion barrier being coated on the outside surface of the metal liner in another embodiment. The diffusion barrier is a coating of chromium or a chromium alloy and serves to prevent any alloying or formation of low melting eutectic liquid phases between the metal liner and the cladding at elevated temperatures. The metal liner is selected from the group consisting of stainless steel, copper, copper alloys, nickel, and nickel alloys.

Abstract: Means are provided to minimize crud buildup at the interface between the tie plate and end plug in a nuclear fuel bundle. The means may comprise serrations in the end plug and/or serrations in the surface of the tie plate which serrations provide a flow of coolant through the end plug receptacles. A bleed hole extending into the interior of the tie plate may be provided to provide coolant circulation through any blind holes that may be in a tie plate.

Abstract: A novel aqueous electrolytic activating solution and a method for electroplating zirconium and zirconium alloys are disclosed. The novel aqueous electrolytic activating solution is comprised of from about 10 to about 20 grams per liter of ammonium bifluoride (NH.sub.4 FHF) and from about 0.75 to 2 grams per liter of sulfuric acid (H.sub.2 SO.sub.4).

Abstract: A process for separately recovering uranium, plutonium and neptunium substantially free of fission products from irradiated nuclear fuel is presented in which the fuel is dissolved in a strong mineral acid forming an aqueous dissolved nuclear fuel solution and treated to separate the uranium, plutonium and neptunium therefrom substantially free of said fission products by the sequential steps of solvent extraction, ion exchange and fluorination. The process has an improvement comprising the addition of a sufficient quantity of an additive of a stable metallic complex to the aqueous dissolved nuclear fuel solution prior to solvent extraction. This achieves improved purity of the separated uranium, plutonium and neptunium.

Abstract: A system for on-site, non-destructive examination of the seam welds or other portions of the walls of a vessel, for example, a nuclear reactor pressure vessel, including an instrument carrying, remotely controlled vehicle with magnetic adherence means which may be selectively propelled to any position on the walls of the vessel and including an ultrasonic signal system utilizing a triangulation technique for remotely indicating the position of the vehicle on the vessel.

Abstract: An improved process for the conversion of gaseous uranium hexafluoride to a uranium oxide rich composition in the presence of an active flame in a reaction zone is disclosed and comprises introducing a first gaseous reactant comprising a mixture of uranium hexafluoride and an oxygen-containing carrier gas and a second gaseous reactant comprising a reducing gas, the reactants being separated by a shielding gas as introduced to the reaction zone. The shielding gas temporarily separates the gaseous reactants and temporarily prevents substantial mixing and reacting of the gaseous reactants. The flame occurring in the reaction zone is maintained away from contact with the inlet introducing the mixture to the reaction zone.

Abstract: Process for dehalogenation of particulate compositions containing halide impurities including metallic oxides and metallic halides such as metallic fluorides to produce metallic oxides by contacting the compositions in a heated atmosphere containing vaporized alcohol. A second gas including inert gases and active dehalogenating gases can be mixed with the vaporized alcohol. A preferred practice has agitation of the particulate compositions containing halide impurities during the dehalogenation process. The metallic oxide produced by dehalogenation can be freed from any hydrocarbon residues where desired by a subsequent heating step in a reducing atmosphere. The halide ions from the dehalogenation can be recovered as an acid by passing the dehalogenation atmosphere through water. A preferred practice of this invention uses propyl alcohol as no hydrocarbon residues are found in the dehalogenated powder.

Abstract: A spacer for positioning at least the four corner fuel rods in a tubular flow channel of a nuclear reactor is disclosed. The spacer comprises a support member having four side bands interconnected by four corner bands to form a unitary structure. Each of the side bands has a L-shaped lobe adjacent each of its ends with one leg of each lobe extending to the adjacent end of its side band. Each of the corner bands is narrower than the side bands and is offset so as to be spaced from the lobe. One leg of each lobe is positioned to engage the tubular flow channel to maintain proper spacing between the flow channel and the adjacent corner fuel rod and to improve the thermal-hydraulic performance of the spacer.

Abstract: A nuclear fuel element for use in the core of a nuclear reactor is disclosed and has disposed therein an improved getter capable of gettering reactive gases including a source of hydrogen. The getter comprises a composite with a substrate having thereon a coating capable of gettering reactive gases. The substrate has a greater coefficient of thermal expansion than does the coating, and over a period of time at reactor operating temperatures any protective film on the coating is fractured at various places and fresh portions of the coating are exposed to getter reactive gases. With further passage of time at reactor operating temperatures a fracture of the protective film on the coating will grow into a crack in the coating exposing further portions of the coating capable of gettering reactive gases.

Abstract: A system for on-site, non-destructive examination of the seam welds or other portions of the walls of a vessel, for example, a nuclear reactor pressure vessel, including an instrument carrying, remotely controlled vehicle with magnetic adherence means which may be selectively propelled to any position on the walls of the vessel and including an ultrasonic signal system utilizing a triangulation technique for remotely indicating the position of the vehicle on the vessel.

Abstract: A method of protecting the cladding of a nuclear fuel element from internal attack and a nuclear fuel element for use in the core of a nuclear reactor are disclosed. The nuclear fuel element has disposed therein an additive of a barium-containing material and the barium-containing material collects reactive gases through chemical reaction or adsorption at temperatures ranging from room temperature up to fuel element plenum temperatures. The additive is located in the plenum of the fuel element and preferably in the form of particles in a hollow container having a multiplicity of gas permeable openings in one portion of the container with the openings being of a size smaller than the size of the particles. The openings permit gases and liquids entering the plenum to contact the particles. The additive is comprised of elemental barium or a barium alloy containing one or more metals in addition to barium such as aluminum, zirconium, nickel, titanium and combinations thereof.

Abstract: This invention presents a process for conversion of gaseous uranium hexafluoride to an oxide product of uranium by introducing to a reaction zone in the presence of an active flame maintained in the reaction zone a first gaseous reactant comprising a mixture of uranium hexafluoride and an oxygen-containing gas and a second gaseous reactant comprising a reducing gas and temporarily separating the first and second gaseous reactants with a shielding gas which temporarily prevents substantial mixing and reaction between these gaseous reactants. The first and second gaseous reactants ultimately react in a primary flame to give a particulate uranium dioxide rich composition and residual reducing gas. An oxygen-containing gas as a third gaseous reactant is introduced through multiple downstream inlets with the inlet closest to the primary flame being at a location in the reaction zone where the uranium hexafluoride conversion to the uranium dioxide rich composition is substantially complete.

Abstract: A nuclear fuel element for use in the core of a nuclear reactor is disclosed. A heat conducting, fission product retaining metal liner of a refractory metal is incorporated in the fuel element between the cladding and the nuclear fuel to inhibit mechanical interaction between the nuclear fuel and the cladding, to isolate fission products and nuclear fuel impurities from contacting the cladding and to improve the axial thermal peaking gradient along the length of the fuel rod. The metal liner can be in the form of a tube or hollow cylindrical column, a foil of single or multiple layers in the shape of a hollow cylindrical column, or a coating on the internal surface of the cladding. Preferred refractory metal materials are molybdenum, tungsten, rhenium, niobium and alloys of the foregoing metals.

Abstract: A method of dehalogenating a particulate composition in a calciner having a heating zone and a cooling zone is presented in which a dehalogenating atmosphere flows through the calciner, including a constricted zone in the calciner, countercurrent to the movement of the composition through the calciner. There is practiced a step of constricting the passage of the controlled atmosphere to a zone of greater flow velocity so that the flow of the dehalogenating atmosphere through the constricted zone substantially minimizes diffusion into the cooling zone of the gaseous impurities removed from the particulate composition in the heating zone.

Abstract: A nuclear fuel element for use in the core of a nuclear reactor is disclosed and has disposed therein an improved getter capable of gettering reactive gases including a source of hydrogen. The getter comprises a composite with a substrate having thereon a coating capable of gettering reactive gases. The substrate has a greater coefficient of thermal expansion than does the coating, and over a period of time at reactor operating temperatures any protective film on the coating is fractured at various places and fresh portions of the coating are exposed to getter reactive gases. With further passage of time at reactor operating temperatures a fracture of the protective film on the coating will grow into a crack in the coating exposing further portions of the coating capable of gettering reactive gases.

Abstract: An expendable restrain device including restraint members positioned in spaced relation around a pressure pipe to limit pipe movement in the event of pipe rupture, the restraint members being designed to undergo plastic elongation to thereby absorb the energy of the pipe.

Abstract: A barrier member fixed in the end of a fuel column retaining spring to prevent contact between the retaining spring and the adjacent end plug of the fuel element whereby contamination of the weld between the cladding tube and end plug with retaining spring material is avoided.