Abstract: A compressed powder composite (CPC) material for absorbing neutrons emitted from spent nuclear fuel thereby preventing the initiation of a chain reaction. The CPC material is typically provided as a substantially insoluble cylindrical pellet that is highly resistant to corrosion and is not subject to the failure modes associated with the alloy materials typically used in neutron absorption materials. The pellet preferably includes a dendritic nickel powder substantially uniformly mixed with a neutron absorber powder material, preferably boron carbide. Tubes filled with CPC materials, such tubes for replacing control roads so that a spent nuclear fuel assembly may be disposed of substantially indefinitely.

Abstract: A tracking and identification card for an air filter specimen, the card having a sheet-like base with a substantially flat support surface for supporting the specimen, the base having a substantially uniform thickness of from about 3 to about 20 mil, and having a focus axis oriented substantially normal to the support surface, a locator area on the support surface and provided with contact adhesive for adhesively holding the specimen in a particular position on the support surface upon contact of the specimen with the adhesive, a sheet-like cover in contact with and substantially overlying the adhesive, the cover being readily removable for exposing the adhesive and allowing the specimen to be placed in contact therewith, and indicia markings on the base for interfacing with an indicia reader for tracking the location and identity of the card within an air monitoring system.

Abstract: A process for reducing the concentration of fissionable uranium containing components of a feed material to below a target concentration level, the process having the steps of providing the feed material as an aqueous system of high-enriched uranyl nitrate hydrate (HE-UNH) wherein at least about 18% of the uranium therein is the .sup.235 U isotope, providing an aqueous dilution medium containing natural uranyl nitrate hydrate (NUNH) wherein at least about 90% of the uranium therein is the .sup.238 U isotope, forcing a diluent stream of the dilution medium through a jet pump to provide a suction region within the pump coextensive with the diluent stream, providing a feed fluid connection of the HE-UNH within the first vessel means with the suction region to cause a HE-UNH stream to flow into the suction region and intermix therein with the diluent stream to form a product stream of markedly reduced .sup.235 U concentration.

Abstract: A system for the collection and use of radiation data on airborne particulate materials, which system provides one or more facets of enhanced data accuracy, security, retrievability, accountability of personnel, chain of custody, or the like, the system having the following components:(a) an airborne material collection filter means having bar code indicia thereon;(b) a computer adapted for storing and/or processing record data and property data;(c) a bar code reader adapted for interfacing with the bar code on the filter means and accessing record data thereon, the reader also being adapted for interfacing with the computer for the transport of record data thereto; and(d) a radiation counter adapted for analyzing and providing radioactivity (property data) on particulate materials collected by the filter means and for interfacing with the computer for the transport of the property data thereto;(e) the computer being adapted for correlating the record data and property data and calculating and reporting work

Abstract: Low density, porous, metal oxide microspheres are prepared from metal salt solutions by sol-gel technique followed by ammonia treatment of the green microspheres, drying, impregnation with fugitive organic material and heat temperature under controlled conditions of temperature and atmosphere. The product metal oxide microspheres have a density of below 70% of their theoretical maximum density and a porosity of at least 0.04 cubic centimeters per gram as measured by mercury penetration technique. Microspheres of hematite, magnetite, and other metal oxides useful as catalysts or as purifying agents to remove contaminants from liquid or gaseous streams may be produced.

Abstract: A cask has an inner rectangular enclosure of stainless steel fitting, with a slight clearance in the similarly shaped interior of a generally rectangular body of depleted uranium serving as a gamma ray shield. A cylindrical shell surrounds the generally rectangular gamma ray shield and copper partitions divide the annular space therebetween into a plurality of compartments for a neutron absorbing liquid. Flow paths between compartments are provided without removing copper from the partitions or interrupting any radial heat conduction path of any partition. Transverse partitions in certain of the compartments provide for holding the radial thickness of the liquid generally uniform throughout the circumference of the cask.

Abstract: A spacer grid for nuclear fuel rods is formed of generally identical metal straps arranged in crossed relation to define a multiplicity of cells adapted to receive elongated fuel elements or the like. The side walls of each cell have openings for intercell mixing of coolant and tabs from edges of the openings defining helical coolant deflectors in the cells. Tabs from adjacent side walls are fixedly secured together to provide rigidifying flanges for the grid. Spring fingers at the ends of the cells provide for holding fuel rods against fixed stops.