Methods for separating radioisotopes from nuclear waste are disclosed. In some embodiments, the methods include separating radioisotopes such as carbon- 14 from spent ion exchange resin. In some embodiments, the methods include separating a variety of commercially useful radioisotopes from spent ion exchange resin.
Methods for recycling metals from nuclear industry components are described. In some embodiments, the methods include removing metal contaminated with radionuclides from a metal component, resulting in a contaminated solution containing the radionuclides, and separating the radionuclides from the contaminated solution. The metal removal can be performed mechanically, chemically, and/or electrochemically. The radionuclides can be separated using techniques such as ion exchange, solvent extraction, precipitation, coprecipitation, and/or electrochemical deposition. Waste materials generated during the recycling process can be reused in subsequent recycling steps. The methods allow the recycling of valuable metals from nuclear industry components while minimizing radioactive waste and allowing the beneficial reuse of recovered radionuclides.
39 - Transport, packaging, storage and travel services
40 - Treatment of materials; recycling, air and water treatment,
Goods & Services
(1) Waste management services, namely transportation and storage of waste; nuclear and radioactive materials waste management services, namely transportation and storage of nuclear and radioactive waste;
(2) Waste management services, namely sorting, treating and recycling waste, destruction and disposal of waste, reclamation of usable material from waste, and technical consulting in the field of waste management; nuclear and radioactive materials waste management services, namely treatment and decontamination of nuclear and radioactive waste, decontamination and remediation of nuclear and radioactive land sites and facilities, consulting in the field of nuclear and radioactive materials waste management;
39 - Transport, packaging, storage and travel services
40 - Treatment of materials; recycling, air and water treatment,
Goods & Services
(1) Waste management services, namely transportation and storage of waste; nuclear and radioactive materials waste management services, namely transportation and storage of nuclear and radioactive waste
(2) Waste management services, namely sorting, treating and recycling waste, destruction and disposal of waste, reclamation of usable material from waste, and technical consulting in the field of waste management; nuclear and radioactive materials waste management services, namely treatment and decontamination of nuclear and radioactive waste, decontamination and remediation of nuclear and radioactive land sites and facilities, consulting in the field of nuclear and radioactive materials waste management
39 - Transport, packaging, storage and travel services
40 - Treatment of materials; recycling, air and water treatment,
Goods & Services
(1) Waste management services, namely transportation and storage of waste; nuclear and radioactive materials waste management services, namely transportation and storage of nuclear and radioactive waste
(2) Waste management services, namely sorting, treating and recycling waste, destruction and disposal of waste, reclamation of usable material from waste, and technical consulting in the field of waste management; nuclear and radioactive materials waste management services, namely treatment and decontamination of nuclear and radioactive waste, decontamination and remediation of nuclear and radioactive land sites and facilities, consulting in the field of nuclear and radioactive materials waste management
40 - Treatment of materials; recycling, air and water treatment,
37 - Construction and mining; installation and repair services
39 - Transport, packaging, storage and travel services
Goods & Services
Waste management services, namely, recycling and processing of nuclear, hazardous, and radioactive waste; Nuclear and radioactive materials waste management services, namely, recycling and processing of nuclear, hazardous, and radioactive waste, and decontamination and remediation of nuclear sited and facilities Waste management services, namely, waste cleaning services; Nuclear and radioactive materials waste management services, namely, nuclear, radioactive, and hazardous waste and cleaning services Waste management services, namely, transport and storage of nuclear, hazardous, and radioactive materials; Nuclear and radioactive materials waste management services, namely, transport and storage of nuclear, hazardous, and radioactive waste
39 - Transport, packaging, storage and travel services
40 - Treatment of materials; recycling, air and water treatment,
Goods & Services
Waste management services, namely, transport of nuclear, hazardous, and radioactive materials; Nuclear and radioactive materials waste management services, namely, transport and storage of nuclear, hazardous, and radioactive waste Waste management services, namely, recycling and processing of nuclear, hazardous, and radioactive waste; Nuclear and radioactive materials waste management services, namely, recycling and processing of nuclear, hazardous, and radioactive waste, and decontamination and remediation of nuclear sited and facilities
39 - Transport, packaging, storage and travel services
40 - Treatment of materials; recycling, air and water treatment,
Goods & Services
Waste management services, namely, transport of nuclear, hazardous, and radioactive materials; nuclear and radioactive materials waste management services, namely, transport and storage of nuclear, hazardous, and radioactive waste Waste management services, namely, recycling and processing of nuclear, hazardous, and radioactive waste; nuclear and radioactive materials waste management services, namely, recycling and processing of nuclear, hazardous, and radioactive waste, and decontamination and remediation of nuclear sited and facilities
9.
Method of using a modular container system for radioactive waste
A packaging system for radioactive waste is robust, highly functional, and can be used for nearly all radioactive waste streams that require shielded packaging. The packaging system includes a modular container that is configured to receive modular shielding inserts. The packaging system can be used to store, transport, and dispose of radioactive waste.
Methods for manufacturing an isotopic filtration module and methods for filtering water according to its isotopic forms. In some implementations, graphene oxide flakes may be dispersed in an aqueous medium to form a graphene oxide solution. The graphene oxide solution may be applied to a substrate to form a laminated graphene oxide membrane comprising a plurality of graphene oxide sheets coupled together in a layered, interlocking structure.
B01D 69/02 - Semi-permeable membranes for separation processes or apparatus characterised by their form, structure or propertiesManufacturing processes specially adapted therefor characterised by their properties
G21F 9/12 - Processing by absorptionProcessing by adsorptionProcessing by ion-exchange
C02F 1/04 - Treatment of water, waste water, or sewage by heating by distillation or evaporation
C02F 1/44 - Treatment of water, waste water, or sewage by dialysis, osmosis or reverse osmosis
B32B 37/24 - Methods or apparatus for laminating, e.g. by curing or by ultrasonic bonding characterised by the properties of the layers with at least one layer not being coherent before laminating, e.g. made up from granular material sprinkled onto a substrate
B01J 20/02 - Solid sorbent compositions or filter aid compositionsSorbents for chromatographyProcesses for preparing, regenerating or reactivating thereof comprising inorganic material
B01J 20/28 - Solid sorbent compositions or filter aid compositionsSorbents for chromatographyProcesses for preparing, regenerating or reactivating thereof characterised by their form or physical properties
Methods for filling a container with hazardous waste are disclosed. One method includes moving the container to a position where a filling head adds solid hazardous waste to the container, coupling a lid to the container to close the container while the container is at the position, and moving the closed container away from the position. Another method includes aerating dry cementitious material in the container with a mixer, adding hazardous waste to the container, mixing the cementitious material and the hazardous waste with the mixer, and controlling the speed of the mixer.
A packaging system for radioactive waste is robust, highly functional, and can be used for nearly all radioactive waste streams that require shielded packaging. The packaging system includes a modular container that is configured to receive modular shielding inserts. The packaging system can be used to store, transport, and dispose of radioactive waste.
Systems for filtering water according to its isotopic forms. In some embodiments, a stream of water, such as a waste stream of water from a nuclear power plant, comprising at least two distinct isotopic forms of water may be directed into one or more filtration modules comprising a graphene oxide membrane. The graphene oxide membrane(s) may be used to separate the stream into a permeate and a retentate, wherein the permeate comprises an increased concentration of light water relative to the retentate.
B01D 29/56 - Filters with filtering elements stationary during filtration, e.g. pressure or suction filters, not covered by groups Filtering elements therefor with multiple filtering elements, characterised by their mutual disposition in series connection
C02F 1/04 - Treatment of water, waste water, or sewage by heating by distillation or evaporation
C02F 1/00 - Treatment of water, waste water, or sewage
C02F 1/44 - Treatment of water, waste water, or sewage by dialysis, osmosis or reverse osmosis
Methods for manufacturing an isotopic filtration module and methods for filtering water according to its isotopic forms. In some implementations, graphene oxide flakes may be dispersed in an aqueous medium to form a graphene oxide solution. The graphene oxide solution may be applied to a substrate to form a laminated graphene oxide membrane comprising a plurality of graphene oxide sheets coupled together in a layered, interlocking structure. The laminated graphene oxide membrane may be positioned in a filtration housing configured to be coupled with a wastewater stream of a nuclear power plant in order to filter the wastewater stream according to its isotopic forms.
C02F 1/44 - Treatment of water, waste water, or sewage by dialysis, osmosis or reverse osmosis
B32B 37/24 - Methods or apparatus for laminating, e.g. by curing or by ultrasonic bonding characterised by the properties of the layers with at least one layer not being coherent before laminating, e.g. made up from granular material sprinkled onto a substrate
G21F 9/12 - Processing by absorptionProcessing by adsorptionProcessing by ion-exchange
B01D 69/02 - Semi-permeable membranes for separation processes or apparatus characterised by their form, structure or propertiesManufacturing processes specially adapted therefor characterised by their properties
B01J 20/02 - Solid sorbent compositions or filter aid compositionsSorbents for chromatographyProcesses for preparing, regenerating or reactivating thereof comprising inorganic material
B01J 20/28 - Solid sorbent compositions or filter aid compositionsSorbents for chromatographyProcesses for preparing, regenerating or reactivating thereof characterised by their form or physical properties
Methods and systems for filtering water according to its isotopic forms. In some embodiments, a stream of water comprising at least two distinct isotopic forms of water may be directed into one or more filtration modules comprising a graphene oxide membrane. The graphene oxide membrane(s) may be used to separate the stream into a permeate and a retentate, wherein the permeate comprises an increased concentration of light water relative to the retentate.
Methods and systems for filtering water according to its isotopic forms. In some embodiments, a stream of water comprising at least two distinct isotopic forms of water may be directed into one or more filtration modules comprising a graphene oxide membrane. The graphene oxide membrane(s) may be used to separate the stream into a permeate and a retentate, wherein the permeate comprises an increased concentration of light water relative to the retentate.
Methods and systems for filtering water according to its isotopic forms. In some embodiments, a stream of water comprising at least two distinct isotopic forms of water may be directed into one or more filtration modules comprising a graphene oxide membrane. The graphene oxide membrane(s) may be used to separate the stream into a permeate and a retentate, wherein the permeate comprises an increased concentration of light water relative to the retentate.
Methods and systems for treatment of wastewater. In some embodiments, the system may comprise one or more modules such as an electrochemical module, an electrocoagulation module, a flotation module, an evaporation module, and an ultrafiltration module. One or more detection modules may also be provided to analyze the concentration of one or more wastewater components in the wastewater. Data from such modules may be used to adjust one or more operational parameters or conditions in the treatment system. The system may also comprise one or more features designed to minimize adverse effects on the environment, such as avoiding adding chemicals to the stream, extracting salt or other chemicals for re-use, and/or use of carbon dioxide gas from on-site combustion processes.
G05B 13/00 - Adaptive control systems, i.e. systems automatically adjusting themselves to have a performance which is optimum according to some preassigned criterion
C02F 1/04 - Treatment of water, waste water, or sewage by heating by distillation or evaporation
C02F 1/24 - Treatment of water, waste water, or sewage by flotation
Methods and systems for treatment of wastewater. In some embodiments, the system may comprise one or more modules such as an electrochemical module, an electrocoagulation module, a flotation module, an evaporation module, and an ultrafiltration module. One or more detection modules may also be provided to analyze the concentration of one or more wastewater components in the wastewater. Data from such modules may be used to adjust one or more operational parameters or conditions in the treatment system. The system may also comprise one or more features designed to minimize adverse effects on the environment, such as avoiding adding chemicals to the stream, extracting salt or other chemicals for re-use, and/or use of carbon dioxide gas from on-site combustion processes.
A system for filling a container with hazardous waste, such as radioactive hazardous waste, includes a primary confinement chamber that houses a lid handling mechanism and a filling head The lid handling mechanism may be used to remove and/or recouple the lid to the container as part of the process of filling the container in such a way to ensure the exterior of the container is not contaminated by the hazardous waste The filling head may be configured to add the hazardous waste to the container, mix the contents of the container, and/or vent air from the container The system may include additional mechanisms to add dry cementitious material to the container, add premixed wet cementitious materials to the container, add cementitious material to seal off the top of the lid, and/or measure the level and test whether the contents of the container meet quality assurance requirements.
A method and apparatus for treating radioactive waste water containing contaminating ions, colloids and suspended solids having like (usually negative) charges preventing their precipitation. An electric current is passed through the waste water in an EC assembly to cause electro-coagulation of the contaminants and anodes of this assembly are made of a metal that dissolves to provide cations for neutralizing the negative charges and forming precipitates containing neutralized contaminants. Precipitates are then separated from waste water by an electro-magnetic or other filtering unit. The water pH and conductivity may be adjusted before the EC assembly and additives may be introduced into its effluent for enlargement of precipitate particles, improvement of filtration, improvement of dewaterability, and/or enhancement of magnetism.
37 - Construction and mining; installation and repair services
39 - Transport, packaging, storage and travel services
40 - Treatment of materials; recycling, air and water treatment,
42 - Scientific, technological and industrial services, research and design
Goods & Services
Nuclear power plants and apparatus; plant, equipment and apparatus for the processing of nuclear fuel; plant, equipment and apparatus for handling, storing, processing and/or disposing of nuclear/radioactive waste materials. Construction, installation, maintenance, repair, defuelling and decommissioning of nuclear power plants and related plant, equipment and apparatus, and of other facilities which involve the use of nuclear/radioactive materials or which generate radioactive waste materials. Packaging, storing and transportation of nuclear fuel and of plant, equipment and apparatus which is or has been contaminated by nuclear/radioactive materials; packaging, storing and transportation of all types of nuclear waste materials. Processing, treatment, recycling and/or disposal [treatment of waste] of nuclear waste materials; decontamination, recycling and/or disposal [treatment of waste] of nuclear plant and of nuclear/radioactive waste materials. Technical analysis, research, technical consultancy, design, engineering, inspections and monitoring in the field of nuclear power, including the design and development of relevant software, and in relation to the handling, storage, transportation, processing, treatment, recycling and/or disposal of radioactive/nuclear waste materials; technical project management and technical consultancy in relation to projects requiring the handling, storage, transportation, processing, treatment, recycling and/or disposal of radioactive/nuclear waste materials; provision of design work and design consultancy in relation to the handling, storage, transportation, processing, treatment, recycling and/or disposal of radioactive/nuclear waste materials; technical management, namely running of nuclear power plants and related plant, equipment and apparatus, and of other facilities which involve the use of nuclear/radioactive materials or which generate radioactive waste materials.
37 - Construction and mining; installation and repair services
39 - Transport, packaging, storage and travel services
40 - Treatment of materials; recycling, air and water treatment,
42 - Scientific, technological and industrial services, research and design
Goods & Services
Nuclear power plants and apparatus; plant, equipment and apparatus for the processing of nuclear fuel; plant, equipment and apparatus for handling, storing, processing and/or disposing of nuclear/radioactive waste materials. Construction, installation, maintenance, repair, defuelling and decommissioning of nuclear power plants and related plant, equipment and apparatus, and of other facilities which involve the use of nuclear/radioactive materials or which generate radioactive waste materials. Packaging, storing and transportation of nuclear fuel and of plant, equipment and apparatus which is or has been contaminated by nuclear/radioactive materials; packaging, storing and transportation of all types of nuclear waste materials. Processing, treatment, recycling and/or disposal [treatment of waste] of nuclear waste materials; decontamination, recycling and/or disposal [treatment of waste] of nuclear plant and of nuclear/radioactive waste materials. Technical analysis, research, technical consultancy, design, engineering, inspections and monitoring in the field of nuclear power, including the design and development of relevant software, and in relation to the handling, storage, transportation, processing, treatment, recycling and/or disposal of radioactive/nuclear waste materials; technical project management and technical consultancy in relation to projects requiring the handling, storage, transportation, processing, treatment, recycling and/or disposal of radioactive/nuclear waste materials; provision of design work and design consultancy in relation to the handling, storage, transportation, processing, treatment, recycling and/or disposal of radioactive/nuclear waste materials; technical management, namely running of nuclear power plants and related plant, equipment and apparatus, and of other facilities which involve the use of nuclear/radioactive materials or which generate radioactive waste materials.
A fill head for depositing hazardous waste materials into a container movable between a filling position seated on the container, and a container exchange position withdrawn from the container; a control arm carried by the fill head directing movement of the fill head between the filling and exchange positions; a drip tray movably carried on a support platform adjacent the fill head for extending underneath the fill head to retain drippings of the hazardous waste material from the fill head when in the exchange position; and, a lifting arm carried by the drip tray engaging the control arm, wherein the lifting arm biases the control arm to raise the fill head from the filling position to the exchange position when the drip tray is extended underneath the fill head so that as the fill head is withdrawn from the container any dripping hazardous waste is captured by the drip tray.
B67C 3/00 - Bottling liquids or semiliquidsFilling jars or cans with liquids or semiliquids using bottling or like apparatusFilling casks or barrels with liquids or semiliquids
30.
MITIGATION OF SECONDARY PHASE FORMATION DURING WASTE VITRIFICATION
A method for vitrification of high level waste to reduce the formation of persistent secondary phases comprising the steps of providing a high level waste for vitrification; providing a glass frit additive for mixing with said high level waste; redistributing selected constituents of said glass frit for mixing separately as raw chemicals with said high level waste; and, feeding said high level waste, said glass frit additive, and the redistributed glass frit constituents to a melter for vitrification of said high level waste so that formation of secondary phases is suppressed.
A method and apparatus for treating radioactive waste water containing contaminating ions, colloids and suspended solids having like (usually negative) charges preventing their precipitation. An electric current is passed through the waste water in an EC assembly to cause electro-coagulation of the contaminants and anodes of this assembly are made of a metal that dissolves to provide cations for neutralizing the negative charges and forming precipitates containing neutralized contaminants. Precipitates are then separated from waste water by an electro-magnetic or other filtering unit. The water pH and conductivity may be adjusted before the EC assembly and additives may be introduced into its effluent for enlargement of precipitate particles, improvement of filtration, improvement of dewaterability, and/or enhancement of magnetism.
A method and apparatus for treating radioactive waste water containing contaminating ions, colloids and suspended solids having like (usually negative) charges preventing their precipitation. An electric current is passed through the waste water in an EC assembly to cause electro-coagulation of the contaminants and anodes of this assembly are made of a metal that dissolves to provide cations for neutralizing the negative charges and forming precipitates containing neutralized contaminants. Precipitates are then separated from waste water by an electro-magnetic or other filtering unit. The water pH and conductivity may be adjusted before the EC assembly and additives may be introduced into its effluent for enlargement of precipitate particles, improvement of filtration, improvement of dewaterability, and/or enhancement of magnetism.
A lifting handle tool including a pair of laterally extending support plate each having a major portion for extending over a top of the lid and a minor portion less than the major portion for overhanging the lid. A handle bar is carried between the support plates at the minor portion for overhanging the lid. A reinforcing bar is carried by the support plates at the major portion for resisting separation and torque of the support plates during lifting. A lifting plate is fixed between the support plates at the minor portion and protrudes vertically below the support plates for extending beneath a lip of the container lid. The lifting plate includes a lip receiving channel for engaging the lip so that applying an upward force to the handle bar causes the support plates to pivot and engage the lip in the lip receiving channel to raise the container lid.
