Kurion, Inc.

Veolia Nuclear Solutions, Inc.

Mtn Group, LLC

Energysolutions Diversified Services, Inc.

Other

Mark Slater Denton

Joshua Leighton Mertz

David K Carlson

Ja-Kael Luey

Gary Hofferber

Zechariah James Fitzgerald

Ronald Merritt Orme

Eric Vincent Penland

James Fredrickson

John Raymont

Jeffrey Theorin Prince

Wesley L Bratton

Hubert W Arrowsmith

Gaetan Bonhomme

Nicephore Bonnet

Trevor Zimmerman

John M Raymont, Jr

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.

Mobile processing system for hazardous and radioactive isotope removal

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.

Advanced tritium system and advanced permeation system for separation of tritium from radioactive wastes

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.

Multi-vessel filtration system for hazardous or radioactive waste water

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.

Selective regeneration of isotope-specific media resins in systems for separation of radioactive isotopes from liquid waste materials

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.

Surface or submersible sluiceable filtration system for hazardous or radioactive waste water

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.

Isotope-specific separation and vitrification

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).

Submersible filters for use in separating radioactive isotopes from radioactive waste materials

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.

Isotope-specific separation and vitrification using ion-specific media

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.

Method for treating radioactive waste water

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.

Growing community of inventors

Knoxville, TN, United States of America

Mark Slater Denton