Abstract: A method for manipulating ion concentration to maximize ion exchange media performance is disclosed herein. First a source liquid is directed through an ion concentrator such as a nanofilter, reverse osmosis membrane, or an evaporator/crystallizer. The ion concentrator separates the source liquid into a concentrate stream and a permeate stream wherein the permeate stream comprises a smaller concentration of ions than the concentrate stream. The concentrate stream and/or the permeate stream (input stream) may then be directed through an ion exchange vessel. The ion exchange vessel receives the input stream, enables ion exchange between the ion exchange media in the vessel and the input stream resulting in a liquid output having a smaller concentration of ions than the input stream.

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 sealing system for isolating the environment inside a vitrification container from the outside environment comprises a vitrification container with a lid. The lid comprises two or more electrode seal assemblies through which two or more electrodes may be operatively positioned and extend down through the lid into the vitrification container. The electrodes may move axially up and down through the electrode seal assemblies or lock into place. The electrode seal assemblies each comprise a housing having two halves with recessed ring grooves. Sealing rings with a split may be placed into the grooves. Gas galleries may be machined or cast into the housing such that they are adjacent to the ring grooves. The gas galleries distribute gas onto the external faces of the sealing rings causing a change in pressure resulting in the sealing rings compressing onto the electrodes and forming a seal.

Abstract: Disclosed herein are systems and methods for a robotic system capable of carrying out operations in a hazardous or confined space. The system comprises a manipulator arm, a plinth, a trolley, an end effector, and a control system. The plinth and trolley each comprise one or more locking pawls for securing the system to mounting points. The system is capable of maneuvering between mounting points in an inch-worm-like fashion. Motion starts from a fixed position where both the trolley and plinth locking pawls are secured to a first mounting point. The trolley locking pawls are then released and the trolley runs along the manipulator and secures locking pawls to a second mounting point. The plinth locking pawls are then released and the plinth is drawn to the second mounting point where it is secured via locking pawls. When both the plinth and trolley are secured, operations can be carried out.

Abstract: A method and an apparatus for automatically collecting and processing nondestructive test (NDT) data to determine the presence, type, location, size, and strength of defects in composite, honeycomb, and grid structures like those found in aircraft, wind blades, boats, cars, building structures. The preferred embodiment is comprised of an uncooled IR mounted on a frame, a conductive heating mat, an IR Ruler with fiducials in a recognizable pattern, a computer, a processor, and output displays. The data collection, processing, and display output can be controlled or reviewed remotely via the internet. The processing, location, and output displays can be applied to any NDT system that collects and processes a two-dimensional amplitude image (e.g., x-ray systems).

Abstract: A method and an apparatus for automatically collecting and processing nondestructive test (NDT) data to determine the presence, type, location, size, and strength of defects in composite, honeycomb, and grid structures like those found in aircraft, wind blades, boats, cars, building structures. The preferred embodiment is comprised of an uncooled IR mounted on a frame, a conductive heating mat, an IR Ruler with fiducials in a recognizable pattern, a computer, a processor, and output displays. The data collection, processing, and display output can be controlled or reviewed remotely via the internet. The processing, location, and output displays can be applied to any NDT system that collects and processes a two-dimensional amplitude image (e.g., x-ray systems).

Abstract: Disclosed herein are systems, methods, processes, and apparatuses for treating radioactive waste, through systems designed to bind and dry radioactive media. In some of its various embodiments, the system includes at least one helical screw designed to receive and mix liquid wastes with ion exchange media, as well as convey the resulting slurry through one or more of a binding, dewatering, and drying/off-gassing region.

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: Disclosed herein are systems, methods, processes, and apparatuses for treating radioactive waste, through systems designed to bind and dry radioactive media and to mechanical devices and techniques that are utilized for removal of granular media from confined spaces (vessels and tanks), in some of its various embodiments, the system processes spent ion exchange media for long-term storage.

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: A mobile processing system is disclosed for the removal of radioactive contaminants from nuclear process waste water. The system is fully scalable, modular, and portable allowing the system to be fully customizable according the site-specific remediation requirements. It is designed to be both transported and operated from standard sized intermodal containers or custom designed enclosures for increased mobility between sites and on-site, further increasing the speed and ease with which the system may be deployed. Additionally, the system is completely modular wherein the various different modules perform different forms or stages of waste water remediation and may be connected in parallel and/or in series. Depending on the needs of the particular site, one or more different processes may be used. In some embodiments, one or more of the same modules may be used in the same operation.

Abstract: Systems and methods for dismantling a nuclear reactor are described. In one aspect the system includes a remotely controlled heavy manipulator (“manipulator”) operatively coupled to a support structure, and a control station in a non-contaminated portion of a workspace. The support structure provides the manipulator with top down access into a bioshield of a nuclear reactor. At least one computing device in the control station provides remote control to perform operations including: (a) dismantling, using the manipulator, a graphite moderator, concrete walls, and a ceiling of the bioshield, the manipulator being provided with automated access to all internal portions of the bioshield; (b) loading, using the manipulator, contaminated graphite blocks from the graphite core and other components from the bioshield into one or more waste containers; and (c) dispersing, using the manipulator, dust suppression and contamination fixing spray to contaminated matter.

Abstract: A method and an apparatus for detecting defects in the composite materials of a wind turbine blade or similar type of structure using an infrared (IR) camera. The temperature of the wind turbine blade is changed in such a way as to produce IR intensity changes in the region of the defect that can be visually detected or detected using a computer and signal processing algorithms. The same approach will work on other composite structures such as those found on aircraft.

Abstract: A system and method for tritium separation systems using a mixed bed catalytic exchange process in a Liquid Phase Catalytic Exchange/Closed Loop Continuous Process (LPCE/CLCP) system, that operates as a low temperature and low pressure continuous balanced process, designed to rapidly, economically and safely extract and isolate isotope specific products without generating unwanted products in the form of new waste streams.

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: 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: 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: 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.