Abstract: A panel filter for filtering waste media comprises at least two stacked filtering medium sheets. Each sheet is shaped to have two substantially identically-shaped portions integrally interconnected along an intermediate portion thereof. The stack of filtering medium sheets is folded over upon itself along the intermediate portions of the filtering medium sheets to create an inner central cavity of said stack and mating marginal edges that are secured and sealed together to form an outlet opening at a point along the marginal edges. A filtration conduit is received in the outlet opening of the panel filter and communicates with the inner central cavity of the panel filter.

Abstract: A method and an apparatus for the disposal of low-level radioactive wastes are disclosed. Under the disclosed method, the waste is first introduced into a preconstructed multipurpose container which comprises a polyethylene inner container disposed within an outer concrete shell. Processing of the waste is carried out within the multipurpose container. The filled container is then transported to a disposal site, followed by storage of the waste at the storage disposal site.The claimed apparatus comprises an empty multipurpose storage container for use in the method. The multipurpose container is adapted for receiving and storing low-level radioactive waste, and comprises a polyethylene inner container disposed within an outer concrete shell.

Abstract: The disclosure of the invention is directed to a site survey ground vehicle based apparatus and method for automatically detecting source materials, such as radioactivity, marking the location of the source materials, such as with paint, and mapping the location of the source materials on a site. The apparatus of the invention is also useful for collecting and analyzing samples. The apparatus includes a ground vehicle, detectors mounted at the front of the ground vehicle, and individual detector supports which follow somewhat irregular terrain to allow consistent and accurate detection, and autolocation equipment.

Abstract: In a cask (10) for the transportation and storage of radioactive materials, an improvement in the shielding means (14) which achieves significant savings in weight and increases in payload by the use of pipes of depleted uranium, tungsten or other dense metal, encapsulating polyethylene cores (20a), dispersed in two to four rows of concentric bore holes (20, 21, 22, 23 or 24) around the periphery of the cask body (11) which is preferably made of ductile iron. Alternatively, rods or small balls of these same shielding materials (21a, 22a, 23a and 24a), alone or in combination, are placed in these bore holes. The thickness, number and arrangement of these shielding pipes (20a) or rods (21a, 22a, 23a or 24a) is varied to provide optimum protection against the neutrons and gamma radiation emitted by the particular radioactive material being transported or stored.

Abstract: Firm gel structures are formed from hot aqueous radioactive waste solutions containing boric acid by adding powdered magnesium oxide or magnesium hydroxide followed by addition of calcium oxide or calcium hydroxide. Cement may be introduced after addition of the magnesium compound without interfering with subsequent gel reactions. Product rigidity imparted by the gel enables reduction of typical cement usage up to 50% or more in the processing of radioactive boric acid concentrates. This results in more waste being solidified per container, less exothermic heat generation, greater shipping efficiency, and improved resistance to aqueous leaching of radionuclides.

Abstract: Using a buffered acid catalyst, a cross-linked urea-formaldehyde polymer matrix is formed by catalyzing an aqueous mixture of an urea-formaldehyde concentrate, urea-formaldehyde resin, and powdered urea. The resulting thermoset polymer which possesses, in part, a cyclic structure, is of unusual hardness and has utility, with or without fillers, as a molding or casting material possessing controllable shrinkage characteristics because of uniform molecular structure and formula versatility. The catalyst system may be used for the polymerization or cure of other urea-formaldehyde or polymeric condensation systems.

Abstract: A cross-linked urea-formaldehyde polymer matrix is formed by catalyzing, using a buffered acid as the catalyst, an aqueous mixture of a urea-formaldehyde concentrate, urea-formaldehyde resin, and powdered urea. The resulting thermoset polymer which possesses, in part, a cyclic structure, is of unusual hardness and has utility, with or without fillers, as a molding or casting material possessing controllable shrinkage characteristics because of uniform molecular structure and formula versatility.