A composition to immobilize nuclear containing waste containing at least one radioactive element or alloy of uranium, graphite, magnesium, and aluminum is disclosed. The composition comprises at least one mineral phase forming element or compound for reacting with the at least one radioactive element or alloy. The composition further comprises at least one glass-forming element or compound to form a glass phase that will incorporate waste radioisotopes and impurities that do not react with the mineral phase forming element or compound. A method of using the disclosed composition to immobilize the nuclear containing waste into a solid wasteform is also disclosed.

A method for treating a fluid waste, comprising adding one or more process additives to the fluid waste in an amount sufficient to change the wasteform chemistry is disclosed. The addition step may be chosen from adding a dispersant or a deflocculant an additive to decrease the reactive metal components, to bind fission products and decrease volatilization of toxic or radioactive elements or species during thermal treatment, or to target and react with the fine particle size component of the waste to decrease dusting and immobilize components in a durable phase. After mixing the fluid waste with the described additives the waste is eventually hot-isostatic pressing, to form a durable and stable waste form.

Apparatuses, processes and methods for the separation, isolation, or removal of radioactive isotopes from liquid radioactive waste, these processes and methods employing a plurality of microspheres. In some embodiments, the processes and methods further include the vitrification of the separated isotopes, generally with the plurality of microspheres. Vitrification is often a step in a larger scheme of preparing the radioactive isotopes for long-term storage or other disposition.

This invention relates to the vitrification of radioactive waste products. According to this invention, a glass composition, which is suitable for flammable waste products, such as gloves, working clothes, plastic waste, and rubber, and a method of vitrifying the flammable waste products using the same are provided to significantly reduce the volume of radioactive waste products and to vitrify the flammable waste products using the glass composition, which is suitable for vitrifying the flammable waste products, thereby maximally delaying or completely preventing the leakage of radioactive materials from a molten solidified body.

This invention relates to the vitrification of radioactive waste products. According to this invention, a glass composition that is suitable for mixed waste products, which include flammable waste products, such as gloves, working clothes, plastic waste, and rubber, and low-level radioactive waste products, and a method of vitrifying the mixed waste products using the same are provided to significantly reduce the volume of radioactive waste products and to vitrify the mixed waste products using the glass composition, which is suitable for vitrifying the mixed waste products, thereby maximally delaying or completely preventing the leakage of radioactive materials from a glass solidified body.

This invention relates to the vitrification of radioactive waste products. According to this invention, a glass composition, which is suitable for low-level radioactive waste resins, and a method of vitrifying the low-level radioactive waste resins using the same are provided to significantly reduce the volume of radioactive waste products and to vitrify low-level radioactive waste products using the glass composition, which is suitable for vitrifying the low-level radioactive waste resins, thereby maximally delaying or completely preventing the leakage of radioactive materials from a glass solidified body.

A method for treating before calcination a nitric aqueous solution comprising at least one radionuclide and ruthenium is provided. The method comprises a step for adding to the solution a compound selected from lignins, lignocelluloses, optionally as salts and mixtures thereof.

The present invention provides a method for synergistically vitrifying medium and low-level radioactive glass fibers and combustible solid nuclear waste incineration ashes. According to the chemical composition characteristics of incineration ashes of combustible solid wastes such as glass fibers, cotton, plastic, rubber and absorbent paper produced during the operation of nuclear facilities, the present invention takes the glass fibers as a glass matrix of combustible waste incineration ashes and minimizes the addition of an additive by a combination in different proportions through a synergistic treatment method. A vitrified form provided by the present invention meets the requirements of uniformity, density, impact resistance, chemical durability and the like of radioactive waste vitrified forms.

A hazardous waste canister includes a housing that includes at least one open end and defines an interior volume; and an end cap sized and configured to attach to the at least one open end of the housing to enclose the interior volume. The housing is configured to enclose a plurality of nuclear waste forms within the interior volume, with at least one of the plurality of nuclear waste forms different than at least another of the plurality of nuclear waste forms.

Submersible media filters and submersible columns for use in removing radioactive isotopes and other contaminants from a fluid stream, such as a fluid stream from the primary coolant loop of a nuclear reactor system or a fluid stream from a spent-fuel pool. Generally, these submersible media filters and submersible columns are adapted to be submersed in the fluid stream, and additionally the filters are adapted to be vitrified after use, resulting in a stabilized, non-leaching final waste product with a substantially reduced volume compared to the original filter. In several embodiments, the submersible media filters and submersible columns include isotope-specific media (ISM).