Abstract: A liquid phase catalytic exchange column with a catalyst is configured to receive hydrogen gas. The system uses the catalyst to exchange the hydrogen gas with the tritiated source yielding HT gas and tritiated water. The system monitors tritium content of the tritiated water. When a predetermined tritium level is detected, the tritiated water is released. The system also includes a gaseous permeation system comprising a permeable barrier for the selective extraction of gases.

Abstract: Surface or submersible sluiceable systems are disclosed for use in removing hazardous contaminants or radioactive isotopes from a fluid stream, such as a fluid stream from the primary coolant loop or secondary loop of a nuclear reactor system, or a fluid stream from a spent-fuel pool or pond or hazardous or radioactive contaminants in ground water. Generally, this surface or submersible sluiceable system is adapted to be utilized in a surface skid or submersed in the fluid stream, and additionally the vessels are adapted to be sluiced and reused after use, resulting in a potentially stabilized, non-leaching final waste product with a substantially reduced volume for storage or disposal. The system can be utilized with standard ion exchange beads or preferably with inorganic granular media.

Abstract: Processes, systems, and methods for selectively regenerating an ion exchange resin generally comprises washing the ion exchange resin with an elution agent that encourages only selected contaminants, and especially selected radioactive isotopes, to disengage or decouple from the resin and enter solution in the elution agent, which thereafter is identified as the elution agent solution. The elution agent solution is then passed through a column of isotope-specific media (ISM). When the selected radioactive isotopes within the elution agent solution come into contact with the constituent media isotopes of the ISM, the selected radioactive isotopes are retained on the reactive surface areas of the ISM or within the interstitial spaces of the porous structures of the constituent media isotopes of the ISM. In some embodiments, the constituent media isotopes of the ISM are embedded, impregnated, or coated with the specific radioactive isotope that the particular ISM are adapted to separate.

Abstract: Surface or submersible sluiceable systems are disclosed for use in removing hazardous contaminants or radioactive isotopes from a fluid stream, such as a fluid stream from the primary coolant loop or secondary loop of a nuclear reactor system, or a fluid stream from a spent-fuel pool or pond or hazardous or radioactive contaminants in ground water. Generally, this surface or submersible sluiceable system is adapted to be utilized in a surface skid or submersed in the fluid stream, and additionally the vessels are adapted to be sluiced and reused after use, resulting in a potentially stabilized, non-leaching final waste product with a substantially reduced volume for storage or disposal. The system can be utilized with standard ion exchange beads or preferably with inorganic granular media.

Abstract: Surface or submersible sluiceable system for use in removing hazardous contaminants or radioactive isotopes from a fluid stream, such as a fluid stream from the primary coolant loop or secondary loop of a nuclear reactor system, a fluid stream from a spent-fuel pool or pond or hazardous or radioactive contaminants in ground water. Generally, this surface or submersible sluiceable system is adapted to be utilized in a surface skid or submersed in the fluid stream, and additionally the vessels are adapted to be sluiced and reused after use, resulting in a potentially stabilized, non-leaching final waste product with a substantially reduced volume for storage or disposal. The system can be utilized with any type of media, whether standard ion exchange beads or inorganic granular media.

Abstract: 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.

Abstract: 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).

Abstract: A liquid phase catalytic exchange column with a catalyst is configured to receive hydrogen gas. The system uses the catalyst to exchange the hydrogen gas with the tritiated source yielding HT gas and tritiated water. The system monitors tritium content of the tritiated water. When a predetermined tritium level is detected, the tritiated water is released. The system also includes a gaseous permeation system comprising a permeable barrier for the selective extraction of gases.

Abstract: 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.

Abstract: Processes, systems, and methods for selectively regenerating an ion exchange resin generally comprises washing the ion exchange resin with an elution agent that encourages only selected contaminants, and especially selected radioactive isotopes, to disengage or decouple from the resin and enter solution in the elution agent, which thereafter is identified as the elution agent solution. The elution agent solution is then passed through a column of isotope-specific media (ISM). When the selected radioactive isotopes within the elution agent solution come into contact with the constituent media isotopes of the ISM, the selected radioactive isotopes are retained on the reactive surface areas of the ISM or within the interstitial spaces of the porous structures of the constituent media isotopes of the ISM. In some embodiments, the constituent media isotopes of the ISM are embedded, impregnated, or coated with the specific radioactive isotope that the particular ISM are adapted to separate.

Abstract: Apparatuses, processes and methods for the separation, isolation, or removal of specific radioactive isotopes from liquid radioactive waste, these processes and methods employing isotope-specific media (ISM). In some embodiments, the processes and methods further include the vitrification of the separated isotopes, generally with the ISM; this isotope-specific vitrification (ISV) is often a step in a larger scheme of preparing the radioactive isotopes for long-term storage or other disposition. A variety of ISM are disclosed.

Abstract: Processes, systems, and methods for selectively regenerating an ion exchange resin generally comprises washing the ion exchange resin with an elution agent that encourages only selected contaminants, and especially selected radioactive isotopes, to disengage or decouple from the resin and enter solution in the elution agent, which thereafter is identified as the elution agent solution. The elution agent solution is then passed through a column of isotope-specific media (ISM). When the selected radioactive isotopes within the elution agent solution come into contact with the constituent media isotopes of the ISM, the selected radioactive isotopes are retained on the reactive surface areas of the ISM or within the interstitial spaces of the porous structures of the constituent media isotopes of the ISM. In some embodiments, the constituent media isotopes of the ISM are embedded, impregnated, or coated with the specific radioactive isotope that the particular ISM are adapted to separate.

Abstract: Systems, methods, and processes for a high throughput, low concentration processing of low activity tritiated light water include the electrolysis of at least some of the tritiated water to produce hydrogen and tritium gas. The hydrogen and tritium gas produced by electrolysis in some cases are combined with heated water vapor to increase throughput and passed through a liquid phase catalytic exchange column, which generally includes a catalyst that includes palladium coated with a hydrophobic polymer. As the hydrogen and tritium gas, along with heated water vapor, rise through the LPCE column, the tritium is retained on the catalyst. Deionized wash water passes down the column (i.e., in the opposite direction of the flow of the hydrogen gas and heated water vapor) and carries the retained tritium out of the LPCE column. Useful in separating tritium from radioactive waste materials and from the water from nuclear reactors.

Abstract: A process and system for treating waste water containing contaminants to prevent excessive accumulation on demineralizer media of a driver contaminate capable of such accumulation before another contaminant can reach a predetermined level of accumulation. The waste water is treated upstream of the demineralizer media with removal means for specifically removing the driver contaminant while leaving the other contaminant for subsequent removal by the demineralizer media. The amount of accumulation on the demineralizer media of the other contaminant is monitored, and the supplying of treated waste water to the demineralizer media is terminated when its accumulation reaches the predetermined level.

Abstract: Systems, methods, and apparatuses for separating tritium from radioactive waste materials and the water from nuclear reactors. Some embodiments involve the reaction of tritiated hydrogen gases with water in the presence of a catalyst in a catalytic exchange column, yielding a more concentrated and purified tritiated water product. Some embodiments involve the use of a permeation module, similar in some respects to a gas chromatography column, in which a palladium permeation layer is used to separate tritiated hydrogen gas from a mixture of gases.

Abstract: Apparatuses, processes and methods for the separation, isolation, or removal of specific radioactive isotopes from liquid radioactive waste, these processes and methods employing isotope-specific media (ISM). In some embodiments, the processes and methods further include the vitrification of the separated isotopes, generally with the ISM; this isotope-specific vitrification (ISV) is often a step in a larger scheme of preparing the radioactive isotopes for long-term storage or other disposition. A variety of ISM are disclosed.

Abstract: Systems and methods for reducing the volume of radioactive waste materials through desiccation, pyrolysis and vitrification carried out by microwave heating. The final product of the advanced microwave system is a dryer, denser, compacted waste product. The invention comprises systems in which a layer of waste material is treated by microwaves within a hopper before deposited within the final waste container; systems in which a thin layer of waste material is treated by microwaves after it has been deposited within the final waste container; and systems in which waste material is treated by microwaves within a hopper before being deposited within the final waste container.

Abstract: Systems and processes for reducing the volume of radioactive waste materials through pyrolysis and vitrification carried out by microwave heating and, in some instances, a combination of microwave heating and inductive heating. In some embodiments, the microwave-enhanced vitrification system comprises a microwave system for treating waste material combined with a modular vitrification system that uses inductive heating to vitrify waste material. The final product of the microwave-enhanced vitrification system is a denser, compacted radioactive waste product.

Abstract: A process and system for treating waste water containing contaminants to prevent excessive accumulation on demineralizer media of a driver contaminate capable of such accumulation before another contaminant can reach a predetermined level of accumulation. The waste water is treated upstream of the demineralizer media with removal means for specifically removing the driver contaminant while leaving the other contaminant for subsequent removal by the demineralizer media. The amount of accumulation on the demineralizer media of the other contaminant is monitored, and the supplying of treated waste water to the demineralizer media is terminated when its accumulation reaches the predetermined level.

Abstract: A regenerable inorganic media capable of removing contaminants by catalytic oxidation or reduction, as well as heavy metal adsorption, from well and surface water sources. The specific material is specially-treated microporous battery grade gamma-form electrolytic manganese dioxide, the treatment involving comminuting to a 20-60 mesh size, complete neutralization and washing to remove fines, residual acidity and neutralization products. Certain taste, odor and staining water contaminants such as hydrogen sulfide, iron and manganese can be oxidized and filtered by the media with subsequent removal from the system by simply backwashing with water or water in combination with simple chemicals. Heavy metals are removed by a different adsorption mechanism on the same media followed by regeneration with a dilute acid. Pretreatment of the media with sodium hydrosulfite further allows the removal of residual chlorine.