Patents by Inventor Mark S. Denton

Mark S. Denton has filed for patents to protect the following inventions. This listing includes patent applications that are pending as well as patents that have already been granted by the United States Patent and Trademark Office (USPTO).

  • Patent number: 10940437
    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.
    Type: Grant
    Filed: June 2, 2016
    Date of Patent: March 9, 2021
    Assignee: Veolia Nuclear Solutions, Inc.
    Inventors: Mark S. Denton, Gaetan Bonhomme, Wesley L. Bratton, Nicephore Bonnet
  • Patent number: 10668405
    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.
    Type: Grant
    Filed: September 18, 2018
    Date of Patent: June 2, 2020
    Assignee: MTN Group, LLC
    Inventors: Mark S. Denton, Jeffrey T. Prince
  • Patent number: 10480045
    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.
    Type: Grant
    Filed: May 11, 2016
    Date of Patent: November 19, 2019
    Assignee: Kurion, Inc.
    Inventor: Mark S. Denton
  • Publication number: 20190015762
    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.
    Type: Application
    Filed: September 18, 2018
    Publication date: January 17, 2019
    Inventors: Mark S. Denton, Jeffrey T. Prince
  • Patent number: 10106439
    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.
    Type: Grant
    Filed: November 4, 2015
    Date of Patent: October 23, 2018
    Assignee: MTN Group, LLC
    Inventors: Mark S. Denton, Jeffrey T. Prince
  • Patent number: 10020085
    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.
    Type: Grant
    Filed: April 21, 2016
    Date of Patent: July 10, 2018
    Assignee: KURION, INC.
    Inventor: Mark S. Denton
  • Patent number: 9714457
    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).
    Type: Grant
    Filed: March 26, 2013
    Date of Patent: July 25, 2017
    Assignee: KURION, INC.
    Inventors: Mark S. Denton, Joshua Mertz, Trevor Zimmerman
  • Publication number: 20160310898
    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.
    Type: Application
    Filed: June 2, 2016
    Publication date: October 27, 2016
    Inventors: Mark S. Denton, Gaetan Bonhomme, Wesley L. Bratton, Nicephore Bonnet
  • Publication number: 20160293283
    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.
    Type: Application
    Filed: April 21, 2016
    Publication date: October 6, 2016
    Applicant: Kurion, Inc.
    Inventor: Mark S. DENTON
  • Publication number: 20160289790
    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.
    Type: Application
    Filed: May 11, 2016
    Publication date: October 6, 2016
    Applicant: Kurion, Inc.
    Inventor: Mark S. DENTON
  • Patent number: 9437336
    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.
    Type: Grant
    Filed: March 9, 2011
    Date of Patent: September 6, 2016
    Assignee: Kurion, Inc.
    Inventor: Mark S. Denton
  • Patent number: 9365911
    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.
    Type: Grant
    Filed: March 26, 2013
    Date of Patent: June 14, 2016
    Assignee: Kurion, Inc.
    Inventor: Mark S. Denton
  • Publication number: 20130336870
    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.
    Type: Application
    Filed: April 15, 2013
    Publication date: December 19, 2013
    Applicant: Kurion, Inc.
    Inventors: Mark S. Denton, Walter T. Shmayda
  • Patent number: 8148594
    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.
    Type: Grant
    Filed: August 6, 2007
    Date of Patent: April 3, 2012
    Assignee: EnergySolutions Diversified Services, Inc.
    Inventors: Mark S. Denton, John M. Raymont, Jr., Hubert W. Arrowsmith
  • Publication number: 20110243834
    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.
    Type: Application
    Filed: April 4, 2011
    Publication date: October 6, 2011
    Applicant: KURION, INC.
    Inventor: Mark S. DENTON
  • Publication number: 20110224473
    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.
    Type: Application
    Filed: January 6, 2011
    Publication date: September 15, 2011
    Applicant: KURION, INC.
    Inventor: Mark S. DENTON
  • Publication number: 20110224472
    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.
    Type: Application
    Filed: March 9, 2011
    Publication date: September 15, 2011
    Applicant: KURION, INC.
    Inventor: Mark S. Denton
  • Publication number: 20110224474
    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.
    Type: Application
    Filed: February 28, 2011
    Publication date: September 15, 2011
    Applicant: KURION, INC.
    Inventor: Mark S. DENTON
  • Publication number: 20090038961
    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.
    Type: Application
    Filed: August 6, 2007
    Publication date: February 12, 2009
    Inventors: Mark S. Denton, John M. Raymont, JR., Hubert W. Arrowsmith
  • Patent number: 5082570
    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.
    Type: Grant
    Filed: December 24, 1990
    Date of Patent: January 21, 1992
    Assignee: CSA Division of Lake Industries, Inc.
    Inventors: Irwin R. Higgins, Mark S. Denton