Destruction Or Containment Of Radioactive Waste Patents (Class 588/1)
  • Patent number: 10847277
    Abstract: Plasma reactors and methods are provided for reducing the volume of radioactive nuclear wastes or toxic wastes where the surface contamination is the main source of radioactivity or toxicity. The radioactive or toxic wastes are prepared in the form of small particles and fed into a pulsed plasma reactor operating in fluidized bed configuration. The repetitively pulsed radio-frequency (rf) powered plasma reactor generates high power plasma for pulse duration between 10 ?s-10 ms. During the pulse, the plasma deliver a short burst of intense heat flux to the surface of waste feed particles. Due to the short pulse duration, the heat flux is concentrated on the surface without propagating much to the core of the particles. The localized heat flux preferentially removes the surface contaminants via vaporization. The removed waste in the vapor phase will be transferred out of the reactor where it may undergo additional treatments or disposed accordingly in a reduced volume.
    Type: Grant
    Filed: September 29, 2017
    Date of Patent: November 24, 2020
    Assignee: PlasmaNano Corporation
    Inventor: Jaeyoung Park
  • Patent number: 10839970
    Abstract: The present invention provides a spent nuclear fuel assembly storage including a metal cask which stores a spent nuclear fuel assembly and a container body which stores the metal cask and has a substantially hexagonal tubular shape, and an assembly of the spent nuclear fuel assembly storage containers, and a method of assembling the spent nuclear fuel assembly storage container.
    Type: Grant
    Filed: April 26, 2016
    Date of Patent: November 17, 2020
    Assignees: WATS Co., Ltd., IHI Construction Materials Co., Ltd., MURATA ENGINEERING Co., Ltd.
    Inventors: Yoshio Hida, Hiroaki Kato, Takashi Murata, Masakatsu Uehara
  • Patent number: 9233405
    Abstract: Embodiments of this disclosure relate to tissue digestion and, more particularly, to methods and apparatuses for varying the number, size, and/or location of one or more tissue compartments within a digestive fluid vessel. Some examples include partitions that may be selectively positioned within a vessel (and may be selectively removable from the vessel) to create one or more tissue compartments. The partitions may be positioned, repositioned and rearranged within the vessel to form one or more tissue compartments. The partitions may be solid or include apertures, and may be oriented in horizontally and/or vertically. Alternate embodiments include one or more selectively closeable apertures that permit digestive fluid to circulate along alternate pathways, which can permit tissue digestion with reduced digestive fluid levels. Still further embodiments include baskets that are selectively positionable within the tissue digester.
    Type: Grant
    Filed: March 31, 2015
    Date of Patent: January 12, 2016
    Assignee: Bio-Response Solutions, Inc.
    Inventors: Joseph H. Wilson, Lucas J. Wilson, Samantha J. Sieber, Mark A. Halsey
  • Publication number: 20150073198
    Abstract: A circulation pipe of a chemical decontamination apparatus including a malonic acid injection apparatus and an oxalic acid injection apparatus is connected to a purification system pipe, which is made of carbon steel, of a boiling water nuclear power plant. A malonic acid aqueous solution is injected from the malonic acid injection apparatus into the circulation pipe. An oxalic acid aqueous solution is injected from the oxalic acid injection apparatus into the circulation pipe. A reduction decontaminating solution including a malonic acid of 5200 ppm and an oxalic acid within a range of 50 to 400 ppm is supplied into the purification system pipe through the circulation pipe. Reduction decontamination for an inner surface of the purification system pipe is executed. After the reduction decontamination for the purification system pipe finishes, the malonic acid and oxalic acid included in the solution are decomposed and furthermore, the solution is purified.
    Type: Application
    Filed: August 4, 2014
    Publication date: March 12, 2015
    Inventors: Kazushige ISHIDA, Hideyuki HOSOKAWA, Motohiro AIZAWA
  • Patent number: 8921475
    Abstract: The invention relates to a hardenable dental composition comprising component (A) comprising a cationically hardenable compound, component (B) comprising an initiator being able to initiate the hardening reaction of the cationically hardenable compound, and component (C) comprising a filler, wherein the filler comprises a filler body and a filler surface, the filler surface comprising side groups with polar moieties. The invention also relates to a process of producing the dental composition, to the use of the dental composition as dental impression material and to a method of taking an impression of dental tissue.
    Type: Grant
    Filed: July 19, 2010
    Date of Patent: December 30, 2014
    Assignee: 3M Innovative Properties Company
    Inventors: Joachim W. Zech, Thomas Klettke, Sebastian Zeller, Bernd Kuppermann, Hendrik Grupp
  • Publication number: 20140378733
    Abstract: The present invention provides an oxidative decontamination reagent for removal of the dense radioactive oxide layer on a metal surface, which comprises an oxidizing agent, a metal ion, and an inorganic acid. The oxidative decontamination reagent of the present invention is characteristically prepared by adding a metal ion to the conventional oxidative decontamination reagent containing an oxidizing agent and an inorganic acid. When the oxidative decontamination reagent of the present invention is used, electric potential of the metal parts of the primary system of the nuclear power plant can be regulated as passive potential owing to the added metal ion during the oxidative decontamination of the primary metal part of the nuclear power plant. Therefore, by maintaining electric potential of the metal part as passive potential, local corrosion can be inhibited and at the same time secondary waste can be significantly reduced.
    Type: Application
    Filed: June 13, 2014
    Publication date: December 25, 2014
    Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE
    Inventors: Sang Yoon PARK, Hui-Jun WON, Wangkyu CHOI, Jeikwon MOON, Chong-Hun JUNG, In-Ho YOON, Jun-Young JUNG
  • Patent number: 8905259
    Abstract: A system for storing high level radioactive waste. In one embodiment, the invention can be a system comprising an overpack body extending along a vertical axis and having a cavity for storing high level radioactive waste, the cavity having an open top end and a floor; an overpack lid positioned atop the overpack body to enclose the open top end of the cavity; an air inlet vent for introducing cool air into the cavity, the air inlet vent comprising an annular air inlet plenum and an annular air inlet passageway, the annular air inlet plenum extending radially inward from an outer surface of the overpack body to the annular air inlet passageway, the annular air inlet passageway extending upward from the annular air inlet plenum to an opening in the floor, and an air outlet vent in the overpack lid for removing warmed air from the cavity.
    Type: Grant
    Filed: August 12, 2011
    Date of Patent: December 9, 2014
    Inventors: Krishna P. Singh, John D. Griffiths
  • Publication number: 20140350320
    Abstract: A system and method for processing of carbon-based radioactive waste, comprise at least: a) soaking in an acid solution, and b) a heat treatment, of a thermal shock type, said acid solution recovering radioactive material resulting from said waste at least after the implementation of step b).
    Type: Application
    Filed: December 11, 2012
    Publication date: November 27, 2014
    Inventor: Gerard Laurent
  • Patent number: 8871674
    Abstract: By fibrillated cellulose fibrillated in fiber form and humidified as a water permeable polymeric substance of botanical origin and a radioactive-substance-absorbent obtained by mixing with zeolite as a granulated inorganic porous crystal, radioactive substances released and spilled in a accident etc. in a nuclear facility etc. may be efficiently and easily collected and removed at a low cost.
    Type: Grant
    Filed: October 22, 2012
    Date of Patent: October 28, 2014
    Assignee: Seibu Newspaper Company
    Inventor: Masao Yamada
  • Patent number: 8871991
    Abstract: A method of stabilizing a fuel containing a reactive sodium metal may include puncturing a cladding of a fuel pin enclosing the fuel containing the reactive sodium metal to form an injection passage and an extraction passage. A reaction gas may be injected into the fuel pin through the injection passage to react with the reactive sodium metal to form a stable sodium compound. A ratio of a product gas and a remaining quantity of the reaction gas exiting the fuel pin through the extraction passage is subsequently measured, wherein the product gas is a reaction product of the reaction gas and the reactive sodium metal within the fuel pin. Once the measured ratio indicates that a reaction between the reaction gas and the reactive sodium metal is complete, the injection passage and the extraction passage are sealed so as to confine the stable sodium compound within the fuel pin.
    Type: Grant
    Filed: September 11, 2012
    Date of Patent: October 28, 2014
    Assignee: GE-Hitachi Nuclear Energy Americas LLC
    Inventors: Eric P. Loewen, Brian S. Triplett, Brett J. Dooies
  • Publication number: 20140249345
    Abstract: An aspect of the present disclosure relates to a method for collecting volatile radioactive substances. The method includes irradiating a volatile radioactive substance on or under a contaminated material surface using microwave radiation and vaporizing the volatile radioactive substance, wherein the volatile radioactive substance comprises at least one of cesium and iodine. The method further includes recovering the vaporized volatile radioactive substance from the contaminated material. The method may be accomplished with and/or without physically collecting or isolating the contaminated material.
    Type: Application
    Filed: December 3, 2012
    Publication date: September 4, 2014
    Applicant: SOUTHWEST RESEARCH INSTITUTE
    Inventor: Southwest Research Institute
  • Patent number: 8772565
    Abstract: A radioactive waste acid is recycled. The waste acid is a fluoboric waste acid. The waste acid contains a lot of oxides and radioactive nuclei. The waste fluoboric acid is processed to obtain a purified fluoboric acid. The amount of radioactive nuclei is greatly reduced. Thus, the present invention has a simple procedure with low cost and reduced power consumption.
    Type: Grant
    Filed: July 3, 2013
    Date of Patent: July 8, 2014
    Assignee: Institute of Nuclear Energy Research, Atomic Energy Council
    Inventors: Chin-Hsiang Kan, Wen-Cheng Lee, Tsong-Yang Wei
  • Patent number: 8742195
    Abstract: The present disclosure describes solid waste forms and methods of processing waste. In one particular implementation, the invention provides a method of processing waste that may be particularly suitable for processing hazardous waste. In this method, a waste component is combined with an aluminum oxide and an acidic phosphate component in a slurry. A molar ratio of aluminum to phosphorus in the slurry is greater than one. Water in the slurry may be evaporated while mixing the slurry at a temperature of about 140-200° C. The mixed slurry may be allowed to cure into a solid waste form. This solid waste form includes an anhydrous aluminum phosphate with at least a residual portion of the waste component bound therein.
    Type: Grant
    Filed: February 26, 2004
    Date of Patent: June 3, 2014
    Assignee: CH2M Hill, Inc.
    Inventors: Arun Wagh, Martin D. Maloney
  • Patent number: 8718221
    Abstract: An apparatus and method for inter-unit transfer of spent nuclear fuel. In one aspect, the invention is a method of transferring high level radioactive waste comprising: a) loading high level radioactive waste into a water-filled cavity of a canister body having an open top end at a first location; b) coupling a lid to the canister body to enclose the open top end; c) removing a volume of water from the cavity so that a water level of the water within the cavity is above a top end of the high level radioactive waste and a space exists between the water level and a bottom surface of the lid; d) hermetically sealing the cavity; and e) transferring the canister to a second location, the water level remaining above the top end of the high level radioactive waste during the transfer.
    Type: Grant
    Filed: December 16, 2010
    Date of Patent: May 6, 2014
    Inventors: Krishna P. Singh, John D. Griffiths
  • Patent number: 8718220
    Abstract: A system and method for storing multiple canisters containing high level waste below grade that afford adequate ventilation of the spent fuel storage cavity. In one aspect, the invention is a ventilated system for storing high level waste emitting heat, the system comprising: an air-intake shell forming an air-intake cavity; a plurality of storage shells, each storage shell forming a storage cavity; a lid positioned atop each of the storage shells; an outlet vent forming a passageway between an ambient environment and a top portion of each of the storage cavities; and a network of pipes forming hermetically sealed passageways between a bottom portion of the air-intake cavity and at least two different openings at a bottom portion of each of the storage cavities such that blockage of a first one of the openings does not prohibit air from flowing from the air-intake cavity into the storage cavity via a second one of the openings.
    Type: Grant
    Filed: February 19, 2010
    Date of Patent: May 6, 2014
    Inventor: Krishna P. Singh
  • Patent number: 8712001
    Abstract: A fuel basket spacer, and system and method for storing high level radioactive waste. In one aspect, the invention is an apparatus for transporting and/or storing radioactive materials comprising: a body having a cavity for receiving radioactive materials; a basket positioned in the cavity comprising a plurality of cells; and a structure having an outer surface and an inner surface forming a central passageway; the structure positioned in the cavity so that the basket extends through the central passageway of the structure; and wherein the internal perimeter of the structure corresponds to the external perimeter of the basket in size and shape and the external perimeter of the structure corresponds to the perimeter of the cavity in size and shape. Circumferential clearances are provided between structure and the basket and the structure and the body that are eliminated when exposed to a residual heat load of the radioactive waste.
    Type: Grant
    Filed: July 2, 2007
    Date of Patent: April 29, 2014
    Inventors: Krishna Singh, Stephen Agace
  • Publication number: 20140073829
    Abstract: A method of stabilizing a fuel containing a reactive sodium metal may include puncturing a cladding of a fuel pin enclosing the fuel containing the reactive sodium metal to form an injection passage and an extraction passage. A reaction gas may be injected into the fuel pin through the injection passage to react with the reactive sodium metal to form a stable sodium compound. A ratio of a product gas and a remaining quantity of the reaction gas exiting the fuel pin through the extraction passage is subsequently measured, wherein the product gas is a reaction product of the reaction gas and the reactive sodium metal within the fuel pin. Once the measured ratio indicates that a reaction between the reaction gas and the reactive sodium metal is complete, the injection passage and the extraction passage are sealed so as to confine the stable sodium compound within the fuel pin.
    Type: Application
    Filed: September 11, 2012
    Publication date: March 13, 2014
    Applicant: GE-HITACHI NUCLEAR ENERGY AMERICAS LLC
    Inventors: Eric P. LOEWEN, Brian S. TRIPLETT, Brett J. DOOIES
  • Patent number: 8541640
    Abstract: Process for the destruction of toxic residues via oxidation in the presence of water and oxygen developed in homogenous phase at temperatures over 374° C. and pressure of at least 220 atmospheres and a continuous mobile unit easily transferred to treat effluents or contaminated media. This mobile unit is composed of a reactor, which includes pressurization, reaction, cooling, depressurization and sampling zones for the destruction of toxic residues like polychloride biphenyls (PCBs), pyridines, and other hazardous compounds.
    Type: Grant
    Filed: December 17, 2009
    Date of Patent: September 24, 2013
    Assignee: Universidad del Valle
    Inventors: Gustavo Eduardo Bolanos Barrera, Victor Fernando Marulanda Cardona
  • Publication number: 20130237741
    Abstract: A decontamination method of solid-state material contaminated by radiocesium comprising bringing the solid-state material containing radiocesium in contact with a first processing solution and preferably eluting cesium ion from the solid-state material to the liquid phase under the presence of potassium ion or ammonium ion.
    Type: Application
    Filed: November 7, 2012
    Publication date: September 12, 2013
    Applicants: Swing Corporation, Ebara Industrial Cleaning Co., Ltd.
    Inventors: Tomokazu Sekine, Tatsuo Shimomura, Takahiro Miama, Daichi Sakashita, Kenichi Futami
  • Publication number: 20130211172
    Abstract: Methods for partially decontaminating radioactive waste wherein the waste is first mixed, or brought in contact, with at least one corrosive medium. Activation energy is then supplied to the corrosive medium, so that at least a portion of the radionuclide present in the waste is converted into at least one gaseous reaction product, or is dissolved, by hydrogen or hydrogen ions, oxygen or oxygen ions, and/or halogen (for example chlorine) or halogen ions from the corrosive medium. The aim is that of decontaminating a 12C/13C-containing porous solid waste, which is contaminated with the 14C radionuclide. For this purpose, CO2 and/or hydrogen are applied as corrosive media to the waste, so that at least a portion of the waste is reacted to form at least one gaseous reaction product, wherein the process temperature is selected so that the 14C radionuclide is enriched in the reaction product over 12C/13C.
    Type: Application
    Filed: July 6, 2011
    Publication date: August 15, 2013
    Inventors: Werner F. Lensa, Dirk Vulpius, Hans-Juergen Steinmetz, Kathrin Baginski, Rahim Nabbi
  • Patent number: 8476481
    Abstract: A method for treating a radioactive liquid waste containing a sodium salt, which includes: feeding a radioactive liquid waste containing at least one of sodium hydroxide, sodium hydrogencarbonate and sodium carbonate to an anode chamber in an electrolytic cell provided with an anode and a cathode on both sides of a permeable membrane, which is selectively permeable to sodium ions, and electrodialyzing the radioactive liquid waste; separating sodium ions permeated through the permeable membrane as sodium hydroxide from the radioactive liquid waste in a cathode chamber; separating a radioactive substance remaining in the anode chamber as a concentrated radioactive liquid waste; and recovering the separated sodium hydroxide and concentrated radioactive liquid waste, respectively.
    Type: Grant
    Filed: November 28, 2008
    Date of Patent: July 2, 2013
    Assignee: JGC Corporation
    Inventors: Yasutomi Morimoto, Mamoru Numata, Takashi Kato
  • Patent number: 8440876
    Abstract: A chemical decontamination apparatus of the present invention chemically dissolves radioactive substance-containing oxide films formed or adhering on the surface of a decontamination object by using ozone water to conduct decontamination. The chemical decontamination apparatus includes an ozone generating unit for generating ozone gas, an ozone supplying device for supplying the generated ozone gas to an ozone supplying unit in water, and a sintered metal element 37 which is disposed in the ozone supplying unit and to which ozone gas is supplied from the ozone supplying device. The ozone gas supplied to a sintered metal element interior from the ozone supplying device is allowed to flow out of the element into water so as to generate ozone water.
    Type: Grant
    Filed: February 6, 2007
    Date of Patent: May 14, 2013
    Assignee: Kabushiki Kaisha Toshiba
    Inventors: Masami Enda, Nagayoshi Ichikawa, Masayuki Kaneda, Takeshi Kanasaki, Toshihiro Yoshii, Yumi Yaita, Ichiro Inami
  • Patent number: 8404191
    Abstract: Biowaste sterilizers are described. In one implementation an exemplary system has waste transport vessels that can be intermittently heated and pressurized, for example, with steam, and are interconnected to provide multiple sterilization pathways for waste as the waste is transported. Selected sterilization pathways may depend on attributes of the waste. Sterilization factors, such as mechanical shredding, application of steam, application of pressure, maintenance of temperature, separation of liquid, etc., are integrated into the waste transport features of the system, which can be made compact to save space while processing relatively large bulk amounts of materials, such as medical wastes. The system maintains safe isolation of bio-hazardous components in the waste from the external environment. A system controller provides parameters management, smart sterilization cycle control, quality assurance, safety management, diagnostics, and reporting over a network.
    Type: Grant
    Filed: September 7, 2012
    Date of Patent: March 26, 2013
    Assignee: Globe-Tek LLC
    Inventor: Donald L Sampson
  • Patent number: 8309784
    Abstract: The present invention relates to a process for the manufacture of a glass frit for the containment by vitrification of a material comprising at least one oxidizable or reducible chemical species, and also to a process for the containment of said material by vitrification. The process for the manufacture of the glass frit comprises a step of incorporating into a raw glass frit at least one redox couple, the nature and the amount of which make it possible to maintain said at least one chemical species in its oxidized or reduced state. The containment process comprises mixing and hot melting the resulting glass frit and the material to be contained. The present invention makes it possible to optimize the containment of pollutants such as radionucleides, metals and metalloids. The material may be nuclear waste or a material derived from the incineration of household refuse.
    Type: Grant
    Filed: July 11, 2006
    Date of Patent: November 13, 2012
    Assignee: Commissariat a l'Energie Atomique
    Inventors: Olivier Pinet, Thierry Blisson, Agnès Grandjean, Sophie Schuller
  • Patent number: 8282892
    Abstract: Bio-waste sterilizers are described. In one implementation an exemplary system has waste transport vessels that can be intermittently heated and pressurized, for example, with steam, and are interconnected to provide multiple sterilization pathways for waste as the waste is transported. Selected sterilization pathways may depend on attributes of the waste. Sterilization factors, such as mechanical shredding, application of steam, application of pressure, maintenance of temperature, separation of liquid, etc., are integrated into the waste transport features of the system, which can be made compact to save space while processing relatively large bulk amounts of materials, such as medical wastes. The system maintains safe isolation of bio-hazardous components in the waste from the external environment. A system controller provides parameters management, smart sterilization cycle control, quality assurance, safety management, diagnostics, and reporting over a network.
    Type: Grant
    Filed: September 23, 2008
    Date of Patent: October 9, 2012
    Assignee: Globe-Tek LLC
    Inventor: Donald L. Sampson
  • Publication number: 20120184795
    Abstract: The present invention provides an apparatus useful for the separation of hazardous and non-hazardous organic and inorganic constituents from various matrices. A method of separating such constituents is also provided.
    Type: Application
    Filed: January 30, 2012
    Publication date: July 19, 2012
    Applicant: IR Systems International
    Inventor: Jeffrey K. O'Ham
  • Patent number: 8211372
    Abstract: An apparatus and system for separating remaining powder of hulls includes a first remaining powder separating unit to be supplied with hulls of a spent nuclear fuel subjected to a high-temperature oxidation, and to include a first brush for separating remaining powder of the hulls; a hull alignment unit to be supplied with the hulls from the first remaining powder separating unit, and to align the hulls; a second remaining powder separating unit to be supplied with the aligned hulls from the hull alignment unit, and to include a second brush for separating remaining powder adhered on an inner peripheral surface of the hulls; and a third remaining powder separating unit to be supplied with the hulls from the second remaining powder separating unit, and to separate the remaining powder remaining on the inner/outer peripheral surface of the hulls by using air.
    Type: Grant
    Filed: February 18, 2010
    Date of Patent: July 3, 2012
    Assignees: Korea Hydro & Nuclear Power Co., Ltd., Korea Atomic Energy Research Institute
    Inventors: Jae-Hoo Jung, Young-Hwan Kim, Byung-Suk Park, Ki Ho Kim, Ji Sup Yoon, Sung-Hyun Kim, Hyo Jik Lee
  • Publication number: 20120121462
    Abstract: The disclosed invention relates to a portable decontamination unit. The invention also relates to a decontamination process. The decontamination unit may be ruggedized for use in hostile environments such as those that may be anticipated for military applications.
    Type: Application
    Filed: January 25, 2012
    Publication date: May 17, 2012
    Inventors: Michael A. Bacik, Aaron L. Hill, Peter J. Buczynski, Richard A. Weiss, Timothy W. Meilander, Paul W. Wiget, Iain F. McVey, Michael A. Centanni
  • Publication number: 20120065453
    Abstract: A radioactive containment composition may be created for containing radionuclides from a radioactive material by mixing a clay mineral with water. This mixture may form an aqueous clay suspension, which in turn can be refined by filtering to remove coarse material. The aqueous clay suspension may be applied to a radioactive material, allowing the radionuclides to be exchanged with cations in the aqueous clay suspension. The resulting aqueous slurry may be collected, heated and analyzed.
    Type: Application
    Filed: February 22, 2011
    Publication date: March 15, 2012
    Inventors: Mark P.S. Krekeler, Stephen C. Elmore
  • Patent number: 8115045
    Abstract: Methods for removing nuclear waste from a component are provided. In one embodiment, the method includes the steps of supplying oxalic acid to the nuclear waste on the component to form an oxalic acid/waste solution, feeding the oxalic acid/waste solution from the component, feeding an oxidant to the oxalic acid/waste solution to form carbon-dioxide, water and a precipitate, and separating the precipitate from the water. A system for removing nuclear waste is also provided.
    Type: Grant
    Filed: November 2, 2007
    Date of Patent: February 14, 2012
    Assignee: AREVA NP Inc.
    Inventors: Sidney Dennis Jones, III, Ray Beatty, John Remark, Wesley Hudson
  • Patent number: 8097164
    Abstract: A process for selectively removing contaminant ions from a solution includes: a) contacting the solution with magnetic particles coupled to selectively chelating ion exchange functionality containing moieties prepared by: i) activating carboxyl groups on the selectively chelating ion exchange functionality containing moieties by the formation of an acyl fluoride, and ii) reacting the acyl fluoride with the magnetic particles, the magnetic particles having a particle size of less than 10 microns; b) allowing the chelating functionality coupled magnetic particles to selectively bind one or more of the contaminant ions; and, c) extracting the chelating functionality coupled magnetic particles and contaminant ions from the solution by magnetic filtration.
    Type: Grant
    Filed: September 17, 2008
    Date of Patent: January 17, 2012
    Assignee: Electric Power Research Institute, Inc.
    Inventors: Sean Paul Bushart, David Bradbury, George Elder, Ilona Pascual
  • Patent number: 8067659
    Abstract: A system, apparatus and method of processing and/or removing radioactive materials from a body of water that utilizes the buoyancy of the water itself to minimize the load experienced by a crane and/or other lifting equipment. In one aspect, the invention is a method comprising: a) submerging a container having a top, a bottom, and a cavity in a body of water having a surface level, the cavity filling with water; b) positioning radioactive material within the cavity of the submerged container; c) raising the submerged container until the top of the containment apparatus is above the surface level of the body of water while a major portion of the container remains below the surface level of the body of water; and d) removing bulk water from the cavity while the top of the container remains above the surface level of the body of water and a portion of the container remains submerged.
    Type: Grant
    Filed: October 11, 2007
    Date of Patent: November 29, 2011
    Inventors: Krishna P. Singh, Stephen J. Agace
  • Patent number: 8048308
    Abstract: The invention relates to a process for separating, in an aqueous medium, at least one actinide element from one or more lanthanide elements by using at least one molecule which sequesters the said actinide element to be separated and membrane filtration, the said process successively comprising: a) a step of bringing at least one molecule which sequesters the said actinide element in contact with the aqueous medium, the said molecule not being retained in the non-complexed state by the said membrane and being capable of forming a complex with the actinide element to be separated, comprising the said element and at least two of the said sequestering molecules, which complex is capable of being retained by the membrane; b) a step of passing the aqueous medium over the membrane in order to form a permeate on one side, comprising an aqueous effluent depleted of the said actinide element, and a retentate comprising the said complex.
    Type: Grant
    Filed: January 30, 2007
    Date of Patent: November 1, 2011
    Assignee: Commissariat a l'Energie Atomique
    Inventors: Gilles Bernier, Jean-Marc Adnet, Alain Favre-Reguillon, Gérard Le Buzit, Marc Lemaire, Stéphane Pellet-Rostaing, Antoine Sorin, Jacques Foos
  • Patent number: 8029738
    Abstract: Methods and devices for removing inflammable gases produced by radiolysis in a closed chamber containing radioactive matters comprising organic compounds and possibly water, or radioactive matters in the presence of organic compounds and possibly water. Inside the chamber there may be placed a catalyst of at least one reaction for oxidizing the inflammable gases by oxygen contained in the chamber atmosphere, supported by an inert solid support; a catalyst of at least the reaction for oxidizing CO to CO2; possibly an oxygen source; and possibly a hygroscopic microporous inert solid support. Also, chambers for radioactive matters containing such devices.
    Type: Grant
    Filed: January 6, 2010
    Date of Patent: October 4, 2011
    Assignee: TN International
    Inventors: Pascale Abadie, Herve Issard
  • Patent number: 7994380
    Abstract: A system, method and apparatus for transporting and/or storing radioactive materials, such as spent nuclear fuel. In one aspect, the invention is a jacket apparatus that is filled with a neutron absorbing fluid and adapted to facilitate a cyclical thermosiphon flow of the neutron absorbing fluid within the jacket when the neutron absorbing fluid is subjected to heat emanating from the cavity. In other aspects, the invention can be a method and container incorporating and/or using the same.
    Type: Grant
    Filed: October 11, 2007
    Date of Patent: August 9, 2011
    Inventors: Krishna P. Singh, Stephen J. Agace
  • Patent number: 7976799
    Abstract: The present invention relates to the use of lithium salts and/or magnesium salts for the precipitation of aluminum oxides present in aqueous media.
    Type: Grant
    Filed: February 24, 2010
    Date of Patent: July 12, 2011
    Assignee: Areva Federal Services, LLC
    Inventor: Donald Geniesse
  • Patent number: 7968067
    Abstract: The present invention relates to the use of lithium salts and/or magnesium salts for the precipitation of aluminum oxides present in aqueous media.
    Type: Grant
    Filed: April 14, 2010
    Date of Patent: June 28, 2011
    Assignee: Areva Federal Services, LLC
    Inventor: Donald Geniesse
  • Patent number: 7951607
    Abstract: The present invention provides methods and compositions for detecting, identifying and measuring the abundance of chemical nerve agents. Methods and compositions of the present invention are capable of providing selective detection of phosphorous based nerve agents, such as nerve agents that are esters of methyl phosphonic acid derivatives incorporating a moderately good leaving group at the phosphorus. Selectivity in the present invention is provided by a sensor composition having an alpha (?) effect nucleophile group that undergoes specific nucleophilic substitution and rearrangement reactions with phosphorus based nerve agents having a tetrahederal phosphorous bound to oxygen. The present invention includes embodiments employing a sensor composition further comprising a reporter group covalently linked to the alpha effect nucleophile group allowing rapid optical readout of nerve agent detection events, including direct visual readout and optical readout via spectroscopic analysis.
    Type: Grant
    Filed: January 21, 2010
    Date of Patent: May 31, 2011
    Assignee: University of Wyoming
    Inventors: Robert C. Corcoran, Aaron D. Strickland
  • Publication number: 20110098521
    Abstract: Method of treating sodium contained in the interconnected open pores of a structure placed in a cladding, the pores furthermore containing a radioactive substance. The method comprises the following successive steps: a) at least two slits are made over the entire length of the cladding; b) the sodium is converted to sodium carbonate by a carbonation reaction by bringing the structure into contact, via the slits, with a reactive gas mixture comprising steam, carbon dioxide and a gas inert with respect to sodium, in such a way that the expansion of the carbonate causes the cladding and the structure to open starting from the slits and results in the carbonation reaction propagating into the structure.
    Type: Application
    Filed: June 24, 2009
    Publication date: April 28, 2011
    Inventors: Serge Sellier, Janick Verdelli, Joel Godlewski, Michel Soucille, Sandrine Poulain
  • Patent number: 7933374
    Abstract: A system and method for storing high level waste. In one aspect, the invention is a system comprising: an outer shell having an open top end and a hermetically closed bottom end; an inner shell forming a cavity, the inner shell positioned inside the outer shell so as to form a space between the inner shell and the outer shell; at least one passageway connecting the space and a bottom portion of the cavity; at least one passageway connecting an ambient atmosphere and a top portion of the space; a lid positioned atop the inner shell, the lid having at least one passageway connecting the cavity and the ambient atmosphere; and a seal between the lid and the inner shell so at form a hermetic lid-to-inner shell interface.
    Type: Grant
    Filed: December 10, 2007
    Date of Patent: April 26, 2011
    Inventor: Krishna P Singh
  • Patent number: 7915472
    Abstract: Clay-based compositions capable of absorbing contaminants from surfaces or objects having surface faces may be applied to a surface and later removed, the removed clay-based compositions absorbing at least a portion of the contaminant from the surface or object to which it was applied.
    Type: Grant
    Filed: February 7, 2006
    Date of Patent: March 29, 2011
    Assignee: Battelle Energy Alliance, LLC
    Inventors: Karen E. Wright, David C. Cooper, Dean R. Peterman, Ricky L. Demmer, Julia L. Tripp, Laurence C. Hull
  • Publication number: 20110065566
    Abstract: The present invention provides an apparatus useful for the separation of hazardous and non-hazardous organic and inorganic constituents from various matrices. A method of separating such constituents is also provided.
    Type: Application
    Filed: August 4, 2010
    Publication date: March 17, 2011
    Applicant: IR Systems International
    Inventor: Jeffrey K. O'Ham
  • Publication number: 20110040137
    Abstract: A rotary-drum mechanical surface decontamination method for radioactively contaminated metal first places a feed chute fully loaded with radioactively contaminated metal on a hydraulic lift platform of a dual-chain roller conveyor and then moves the feed chute to a hydraulic cover-opening machine for positioning, and then uses a hydraulic cover-opening machine to open the cover of the feed chute, while non-covered feed chute will advance further to the post on a feed hopper of a drum spray washer, and then drop the workpieces into a conical drum for rotary multi-angular spray washing. The decontaminated metal waste is transferred by a vibrating discharger onto a conveyor and then into a discharge tank, and to the hydraulic cover-opening machine by a dual-chain roller conveyor, and to the hydraulic lift platform to complete the decontamination process.
    Type: Application
    Filed: August 14, 2009
    Publication date: February 17, 2011
    Inventors: Chin-Hsiang Kan, Tsong-Yang Wei, Kou-Min Lin
  • Publication number: 20100305383
    Abstract: Systems and methods are provided for reducing the storage time of spent nuclear fuel. In one embodiment, a method is provided that includes providing a sample of spent nuclear fuel and irradiating the spent nuclear fuel with substantially collimated gamma ray photons having energy levels of about 10 MeV to about 15 MeV for a predetermined time period to initiate a photofission reaction in the remaining fertile fissile material in the spent nuclear fuel.
    Type: Application
    Filed: May 28, 2009
    Publication date: December 2, 2010
    Inventor: Peter Moshchansky Livingston
  • Patent number: 7835882
    Abstract: The present invention provides a method of online analysis of mineral waste content of a slurry in a mineral separation process, said method including the steps of: measuring the density of said slurry (10); measuring the concentration of solids in said slurry (12); calculating the density of solids in said slurry from said slurry density and said solids concentration (20); and calculating said mineral waste content from said solids density (22). The present invention also provides an online analyzer for mineral waste content of a slurry in a mineral separation process.
    Type: Grant
    Filed: September 20, 2006
    Date of Patent: November 16, 2010
    Assignee: Newcastle Innovation Limited
    Inventor: Noel William Alexander Lambert
  • Publication number: 20100217060
    Abstract: The current methods of removing the surface-deposited layer contaminated by radioisotopes has the disadvantage of rigorous applicability conditions in such terms as the substance to be treated, the area and the shape, so the scope of their applicability is quite limited; in addition, 100% decontamination is not guaranteed and in spite of more than 50% that can be decontaminated, a greater part of the deposited radioisotopes remain unremoved, limiting the decontamination performance of the methods. Parts, structural components, etc. that have their surfaces contaminated by radioisotopes in the accelerators, nuclear reactors, RI product manufacturing factories, nuclear fuel factories, nuclear fuel reprocessing factories, etc.
    Type: Application
    Filed: March 29, 2007
    Publication date: August 26, 2010
    Applicants: Japan Atomic Energy Agency, The Japan Atomic Power Company
    Inventor: Eisuke Minehara
  • Publication number: 20100168497
    Abstract: A chemical decontamination apparatus of the present invention chemically dissolves radioactive substance-containing oxide films formed or adhering on the surface of a decontamination object by using ozone water to conduct decontamination. The chemical decontamination apparatus includes an ozone generating unit for generating ozone gas, an ozone supplying device for supplying the generated ozone gas to an ozone supplying unit in water, and a sintered metal element 37 which is disposed in the ozone supplying unit and to which ozone gas is supplied from the ozone supplying device. The ozone gas supplied to a sintered metal element interior from the ozone supplying device is allowed to flow out of the element into water so as to generate ozone water.
    Type: Application
    Filed: February 6, 2007
    Publication date: July 1, 2010
    Applicant: KABUSHIKI KAISHA TOSHIBA
    Inventors: Masami Enda, Nagayoshi Ichikawa, Masayuki Kaneda, Takeshi Kanasaki, Toshihiro Yoshii, Yumi Yaita, Ichiro Inami
  • Patent number: 7737319
    Abstract: Methods of treating radioactive materials are disclosed. In one aspect, a method may include mixing a radioactive isotope diluted in a filler material with a radioactive material treatment composition to form a resulting material. The radioactive material treatment composition may include mostly salt, and from 0.5 to 15 wt % sorbent. The method may further include mixing the resulting material with one or more inorganic binding agents. Other methods of treating radioactive materials are also disclosed, as well as compositions for treating radioactive materials.
    Type: Grant
    Filed: April 28, 2006
    Date of Patent: June 15, 2010
    Assignee: Llyon Technologies, LLC
    Inventor: Jack W. Matthews
  • Patent number: 7737320
    Abstract: A method of decontaminating porous surfaces contaminated with water soluble radionuclides by contacting the contaminated porous surfaces with an ionic solution capable of solubilizing radionuclides present in the porous surfaces followed by contacting the solubilized radionuclides with a gel containing a radionuclide chelator to bind the radionuclides to the gel, and physically removing the gel from the porous surfaces. A dry mix is also disclosed of a cross-linked ionic polymer salt, a linear ionic polymer salt, a radionuclide chelator, and a gel formation controller present in the range of from 0% to about 40% by weight of the dry mix, wherein the ionic polymer salts are granular and the non cross-linked ionic polymer salt is present as a minor constituent.
    Type: Grant
    Filed: September 28, 2005
    Date of Patent: June 15, 2010
    Assignee: UChicago Argonne, LLC
    Inventors: Michael D. Kaminski, Martha R. Finck, Carol J. Mertz
  • Patent number: 7731912
    Abstract: Disclosed herein is provided an evaporator/calciner in which hazardous materials, such as radioactive liquids, are converted into chemically stable, solid forms by evaporating, drying and calcination within a single vessel, that can then be sealed and used for long term storage.
    Type: Grant
    Filed: September 14, 2007
    Date of Patent: June 8, 2010
    Assignee: Atomic Energy of Canada Limited
    Inventors: Kenneth James Franklin, Andrew Donald Kettner, Bruce Wayne Hildebrandt, Howard Charles Jessup, Jr.