Abstract:
A composition and process for the safe removal and treatment of hazardous waste material is described. This composition is a mixture of grout like cement containing the hazardous waste and a minor amount of an alkali metal silicate and a gelling agent. The hazardous waste is then safely contained within the resulting cementitious material and can be safely disposed by burial, for example. The contaminated wastes are contained within the block and will not be exposed by regular soil actions. This composition and process is particularly useful for treating soil contaminated by low level radioactive materials.
Abstract:
A method of containing hazardous and toxic wastes includes the steps of irporating the dried waste, in a salt form, in melted polymer, such as asphalt, and forming the waste salt and asphalt blend into aggregate pellets. The pellets are coated with a powdered coating material that is compatible with a portland cement-based mortar or other cementitious material which is used. The coated particles are mixed with mortar to form a polymer-aggregate concrete and cast into wasteforms for storage or burial. If it is desirable to produce a waste form with a continuous layer of mortar on the exterior of the concrete monolith the mold can be placed on a turntable and spun, or otherwise exposed to a centrifugal force to force the mortar to the outside of the mold. Centrifugal separation is possible because the polymer-waste mixture typically has a specific gravity near 1.5 while that of the cementitious mixture is typically greater than 2.0.
Abstract:
A method of grouting porous gas--and petroleum--bearing formations with a cementitious material comprising ultrafine ground slag is useful for primary and remedial cementing of a wellbore. A composition is provided which comprises water, a dispersant, slag and an accelerator to activate the slag.
Abstract:
In order to ensure a good seal and a good resistance to shocks and corrosion, without increasing their cost, radioactive waste storage containers are completely made from metal fiber-reinforced concrete. This material is used for producing by molding a drum (210) and a cover (212), as well as a keying joint (224) by which the cover is fixed to the drum. At least one dovetail keying groove is formed in the junction zone between the drum and the cover. Advantageously, a filling material of the same nature as that in which is formed the container is injected into the latter, so as to form a homogeneous block.
Abstract:
A spent, radioactive, organic ion exchange resin is converted into a stable inorganic product having a considerably reduced volume in the following way. The radioactive ion exchange resin is mixed with a salt and an inorganic sorbent for radioactive nucleides, liberated by the salt, the mixture is dried and incinerated, whereupon the ash is solidified in cement.
Abstract:
A method for incorporating radioactive phosphoric acid solutions in concrete is described wherein the phosphoric acid is reacted with Ca(OH).sub.2 to form a precipitate of hydroxyapatite and the hydroxyapatite is mixed with portland cement to form concrete.
Abstract:
Radioactive particles are removed from waste or process water and encapsulated by a filtration process wherein the water is filtered through a filter medium composed of a thermoplastic organic polymer. The filter cake so obtained is dried and converted to a solid encapsulating medium by the application of heat and/or pressure. The filter medium comprises, at least partially, a thermoplastic polymer which is wettable by water but non-swelling in water and has a melting point of 100.degree. to 300.degree. C.
Abstract:
An apparatus is provided for treating various radioactive concentrates having a liquid component, such as suspensions and salt solutions, which are present separately in a processing plant from evaporation systems, resin bead ion exchange filters, and from at least one further separating stage provided with, for example, mechanical filters, sedimentation basins and/or powdered resin ion exchange filters. The filter concentrates containing suspended solids are dewatered in a filter cake-producing filter and the concentrates from the evaporation system (salt solutions) are dewatered wholly or in part directly in transporting and storage drums to the dryness required for storage. At least one of the various concentrates are at least for a time conducted directly (without dewatering) into a storage drum where they are mixed with binders and converted to solids by hardening.
Abstract:
A method for stabilizing radioactive isotopes includes preparing a liquid solution and mixing the liquid solution with Cement Kiln Dust (CKD) powder to form a solid material. The method may further include crushing the solid material into particles and passing radioactive water through the solid material to remove radioactive isotopes from the radioactive water and stabilize the radioactive isotopes.