A manipulator boom assembly for releasable attachment to a manway of a tank. The manipulator boom assembly includes an elongated and curved boom defining an arcuate shape along a length of the boom, a base adapted to be releasably mounted to the manway of the tank, and a drive coupled to the boom, where the boom is movable by the drive relative to the base and the manway between a retracted position and an extended position within the tank.
Systems and methods are disclosed for utilizing lead-tag configuration with ion exchange systems to increase process efficiency, increase media utilization, and reduce system downtime.
Systems and methods are disclosed for controlling performance of a mixed ion exchange media comprising two or more media. The weighted average of a quantity of the first media having a first rate of exchange to a quantity of a second media having a second rate of exchange is determined based on predetermined requirements for the resulting mixed media. After determining the weighted average, the first and second media are mixed resulting in a mixed media having a third rate of exchange. The mixed media is introduced to an ion exchange column. Contaminated liquid is then introduced to the column creating a mass transfer zone within the column. The mixed media is generally considered optimized when it meets three conditions simultaneously: 100% safety limitation, 100% media capacity used, and effluent criteria are met.
B01D 15/36 - Adsorption sélective, p. ex. chromatographie caractérisée par le mécanisme de séparation impliquant une interaction ionique, p. ex. échange d'ions, paire d'ions, suppression d'ions ou exclusion d'ions
C02F 1/28 - Traitement de l'eau, des eaux résiduaires ou des eaux d'égout par absorption ou adsorption
G01N 30/96 - Recherche ou analyse de matériaux par séparation en constituants utilisant l'adsorption, l'absorption ou des phénomènes similaires ou utilisant l'échange d'ions, p. ex. la chromatographie en utilisant l'échange d'ions
B01J 39/00 - Échange de cationsUtilisation d'une substance comme échangeur de cationsTraitement d'une substance en vue d'améliorer ses propriétés d'échange de cations
B01J 41/00 - Échange d'anionsUtilisation d'une substance comme échangeur d'anionsTraitement d'une substance en vue d'améliorer ses propriétés d'échange d'anions
Disclosed herein are systems and methods for a modular reconfigurable shielding system for one or more storage containers in temporary or long term storage. The system comprises shield panels which may be used to shield external faces of containers in a storage configuration to reduce the overall amount of shielding required in a storage facility. Reducing the amount of shielding reduces the storage footprint of each container thus increasing storage capacity and efficiency of the storage facility. The modularity of the shield panels allows storage containers to be easily added and removed from the storage configuration. Additionally, modular shielding allows the amount and type of shielding to be easily reconfigured for differing requirements and storage contents.
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.
A sealing system (300) 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 (250) 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 (310) having two halves with recessed ring grooves(375). Sealing rings (200) with a split may be placed into the grooves. Gas galleries (376) 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.
B09B 3/00 - Destruction de déchets solides ou transformation de déchets solides en quelque chose d'utile ou d'inoffensif
C03B 5/00 - Fusion dans des foursFours, pour autant qu'ils soient spécialement adaptés à la fabrication du verre
C03B 5/027 - Fusion dans des foursFours, pour autant qu'ils soient spécialement adaptés à la fabrication du verre dans des fours électriques par passage d'un courant électrique entre électrodes immergées dans le bain de verre, c.-à-d. par chauffage résistif direct
F16J 15/46 - Joints d'étanchéité par bague de garniture dilatée ou comprimée dans son logement par pression d'un fluide, p. ex. garnitures gonflables
F16J 15/48 - Joints d'étanchéité par bague de garniture dilatée ou comprimée dans son logement par pression d'un fluide, p. ex. garnitures gonflables la pression provenant de celle existant dans l'organe à isoler
F27D 99/00 - Matière non prévue dans les autres groupes de la présente sous-classe
H05B 7/12 - Dispositions pour refroidir, rendre étanche ou protéger les électrodes
7.
Selective regeneration of isotope-specific media resins in systems for separation of radioactive isotopes from liquid waste materials
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.
C02F 103/34 - Nature de l'eau, des eaux résiduaires ou des eaux ou boues d'égout à traiter provenant de l'industrie chimique non prévue dans les groupes
8.
ION SPECIFIC MEDIA REMOVAL FROM VESSEL FOR VITRIFICATION
Disclosed herein are systems (510, 515, 520), methods, processes, and apparatuses for treating radioactive waste, through systems (510, 515, 520) designed to bind and dry radioactive media and to mechanical devices and techniques that are utilized for removal of granular media from confined spaces (300) (vessels and tanks). The system (510, 515, 520) processes spent ion exchange media for long-term storage.
The present disclosure relates to cable routing approaches that allow cables (1000) to pass through a traditional chain joint (100) without reducing the strength capacity or impairing the range of motion of the joint. The routing approaches permit the cables (1000) to be housed inside the structure of the robotic arm (150) and pass through the chain joint in a manner that does not limit the width of the chain (120).
B25J 19/00 - Accessoires adaptés aux manipulateurs, p. ex. pour contrôler, pour observerDispositifs de sécurité combinés avec les manipulateurs ou spécialement conçus pour être utilisés en association avec ces manipulateurs
F15B 15/06 - Schéma mécanique de montage caractérisé par les moyens transformant le mouvement de l'élément entraîné par le fluide en mouvement de l'organe terminal qui est actionné pour la transformation mécanique d'un mouvement rectiligne en un mouvement non rectiligne
10.
MOBILE PROCESSING SYSTEM FOR HAZARDOUS AND RADIOACTIVE ISOTOPE REMOVAL
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.
A62D 3/33 - Procédés pour rendre les substances chimiques nuisibles inoffensives ou moins nuisibles en effectuant un changement chimique dans les substances par réaction avec des agents chimiques par fixation chimique de la substance nuisible, p. ex. par chélation ou complexation
40 - Traitement de matériaux; recyclage, purification de l'air et traitement de l'eau
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
Nuclear waste treatment services for others, namely,
converting waste by vitrification; batch chemical treatment
services; bioremediation services; consulting in the field
of water treatment; decontamination of hazardous materials;
decontamination of nuclear waste; environmental remediation
services, namely, treatment of hazardous and nuclear waste;
waste management services for hazardous materials; nuclear
waste treatment; providing material treatment information;
providing technical information in the field of waste
management; radiation area decontamination services;
treatment of hazardous liquids; treatment of waste water;
treatment of water used in nuclear reactors. Consultation in the field of health risk assessment, namely,
prediction and assessment of health risks to public and
private agencies, facilities, individuals and locations
following an accidental or terrorist caused release of
chemical, biological, radiological or nuclear materials;
scientific consulting services relating to hazardous
materials management; detection of contaminants in waste
water; engineering services and consultation for the
detection of contaminants in waste water; environmental
services, namely, technical consultation in the field of
environmental science; engineering services to support
nuclear and hazardous system characterization, replacement,
modifications, remediation, decommissioning and
deconstruction activities.
12.
A BALANCED CLOSED LOOP CONTINUOUS EXTRACTION PROCESS FOR HYDROGEN ISOTOPES
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.
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.
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-specificmedia (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.
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).
B01D 29/00 - Filtres à éléments filtrants stationnaires pendant la filtration, p. ex. filtres à aspiration ou à pression, non couverts par les groupes Leurs éléments filtrants
B01D 29/46 - Éléments filtrants à arêtes, c.-à-d. utilisant des surfaces imperméables adjacentes à éléments plats empilés
16.
ISOTOPE-SPECIFIC SEPARATION AND VITRIFICATION USING ION-SPECIFIC MEDIA
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.
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.
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.
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.
