Impurity Removal Patents (Class 376/310)
  • Patent number: 10504755
    Abstract: An apparatus for reducing resist residue on a semiconductor substrate surface has a processing tank containing a chemical solution, and two circulation paths arranged in parallel for circulating the chemical solution inside the processing tank. Each circulation path has a pump and a filter. An ozone gas generating device supplies ozone to the processing tank. A third circulation path includes the pump and filter of one of the two circulation paths and is isolated from the processing tank and used to clean the filter by supplying ozone gas to the third circulation path.
    Type: Grant
    Filed: September 13, 2016
    Date of Patent: December 10, 2019
    Assignee: ABLIC Inc.
    Inventor: Ichiro Tamaki
  • Patent number: 10436741
    Abstract: A method of measuring a hydrogen diffusivity of a metal structure is provided. The method includes providing a hydrogen charging surface at a first location on an external surface of the structure, and a hydrogen oxidation surface at a second location adjacent to the first location on the external surface of the structure. A hydrogen flux is generated and directed into the metal surface at the charging surface. At least a portion of the hydrogen flux generated by the charging surface and diverted back toward the surface is detected, and a transient of the diverted hydrogen flux is measured. The hydrogen diffusivity of the metal structure is then determined based on the measured transient.
    Type: Grant
    Filed: April 28, 2017
    Date of Patent: October 8, 2019
    Assignee: Saudi Arabian Oil Company
    Inventors: Kaamil Ur Rahman Mohamed Shibly, Abderrazak Traidia, Abdullah Enezi
  • Patent number: 9752462
    Abstract: A supercritical working fluid closed cycle heat engine includes, in fluid flow series: a heat source heat exchanger configured to raise the temperature of a working fluid; an expander configured to extract work from the working fluid; a condenser configured to exchange heat between the working fluid and the cooling medium; and a separator configured to separate liquid phase working fluid from gaseous phase working fluid and deliver gaseous phase working fluid to a gaseous compressor and liquid phase working fluid to a fixed displacement liquid pump, the compressor and pump being arranged in parallel. Each of the compressor and fixed displacement pump are configured to return fluid to the heat source heat exchanger. The compressor comprises a variable inlet guide vane and a variable outlet diffuser vane.
    Type: Grant
    Filed: February 7, 2017
    Date of Patent: September 5, 2017
    Assignee: ROLLS-ROYCE plc
    Inventor: Paul Fletcher
  • Patent number: 9666320
    Abstract: A tritium removal device for a lithium loop contains a neutron source (1) for colliding protons on a lithium flow, thereby generating neutrons, a lithium tank (11) for the lithium passing through this neutron source (1) to flow thereto through a flow passage (9), thereby temporarily accumulating it therein, and a lithium pump (17) for circulating and supplying the lithium of this lithium tank (11) to the neutron source (1) through a supply-side flow passage (9?). The lithium tank (11) and the lithium pump (17), into which hydrogen gas containing tritium therein can be easily collected, are enclosed within a hermetically sealed container (7) including an inactive gas therein, so that even if the hydrogen gas including the tritium therein is leaked into the hermetically sealed container (7), it is removed by a hydrogen isotope removal filter.
    Type: Grant
    Filed: May 24, 2012
    Date of Patent: May 30, 2017
    Assignees: Sukegawa Electric Co., Ltd., Kyoto University, Tokyo Institute of Technology
    Inventors: Kuniaki Miura, Tooru Kobayashi, Noriyosu Hayashizaki, Nobuo Namiki
  • Patent number: 9440847
    Abstract: A single silicon wafer micromachined thermal conduction sensor is described. The sensor consists of a heat transfer cavity with a flat bottom and an arbitrary plane shape, which is created in a silicon substrate. A heated resistor with a temperature dependence resistance is deposed on a thin film bridge, which is the top of the cavity. A heat sink is the flat bottom of the cavity and parallel to the bridge completely. The heat transfer from the heated resistor to the heat sink is modulated by the change of the thermal conductivity of the gas or gas mixture filled in the cavity. This change can be measured to determine the composition concentration of the gas mixture or the pressure of the air in a vacuum system.
    Type: Grant
    Filed: October 3, 2013
    Date of Patent: September 13, 2016
    Assignee: POSiFA MICROSYSTEMS, INC.
    Inventor: Xiang Zheng Tu
  • Publication number: 20150146839
    Abstract: Systems passively eliminate noncondensable gasses from facilities susceptible to damage from combustion of built-up noncondensable gasses, such as H2 and O2 in nuclear power plants, without the need for external power and/or moving parts. Systems include catalyst plates installed in a lower header of the Passive Containment Cooling System (PCCS) condenser, a catalyst packing member, and/or a catalyst coating on an interior surface of a condensation tube of the PCCS condenser or an annular outlet of the PCCS condenser. Structures may have surfaces or hydrophobic elements that inhibit water formation and promote contact with the noncondensable gas. Noncondensable gasses in a nuclear power plant are eliminated by installing and using the systems individually or in combination. An operating pressure of the PCCS condenser may be increased to facilitate recombination of noncondensable gasses therein.
    Type: Application
    Filed: November 17, 2014
    Publication date: May 28, 2015
    Applicant: GE-HITACHI NUCLEAR ENERGY AMERICAS LLC
    Inventors: Wayne MARQUINO, Stephan C. MOEN, Richard M. WACHOWIAK, John L. GELS, Jesus DIAZ-QUIROZ, John C. BURNS, JR.
  • Patent number: 8824621
    Abstract: A filter including a plurality of flow ducts extending in a longitudinal direction and each delimited between one pair of walls is provided. The filter includes deflectors protruding into each duct alternately from the pair of walls with overlapping in the longitudinal direction to define a zigzag shaped flow channel and provided with at least one set of holes aligned in the longitudinal direction to define through the overlapping deflectors a passage for accommodating a lower end pin of a fuel rod.
    Type: Grant
    Filed: December 29, 2009
    Date of Patent: September 2, 2014
    Assignee: Areva NP
    Inventor: Reazul Huq
  • Patent number: 8798225
    Abstract: A radiation exposure reduction method includes the steps of: injecting iron into a coolant which flows from the reactor cooling system to the reactor core in a nuclear power plant; and ferritizing and fixing radionuclides or parent nuclides thereof, which are contained in the coolant, on the surface of a reactor core structure, wherein an iron citrate which is soluble organic iron, or iron oxalate or iron fumarate which has a particle diameter of 3 ?m or less, is used as the iron to be injected into the coolant.
    Type: Grant
    Filed: November 4, 2009
    Date of Patent: August 5, 2014
    Assignee: Kabushiki Kaisha Toshiba
    Inventors: Yumi Yaita, Seiji Yamamoto, Hajime Hirasawa, Yutaka Uruma
  • Publication number: 20140205052
    Abstract: A chemical decontamination reagent containing a reducing agent, a reductive metal ion, and an inorganic acid is provided to remove a radioactive oxide layer on a metal surface. The reagent can dissolve the radioactive oxide layer on the metal surface effectively at a relatively low temperature and enables a simple process of contacting the reagent to the radioactive oxide, thus economically effective in terms of cost and time required for the process. Since the decontamination does not use a conventional organic chelating agent such as oxalic acid, but the reducing agent as a main substance, the residuals of the reducing agent remained after decontamination can be decomposed and removed with an oxidizing agent. Due to the easy decomposition with the chemical decontamination reagent, secondary wastes can be minimized and the radionuclides remained in the decontamination reagent solution can be removed effectively.
    Type: Application
    Filed: September 4, 2013
    Publication date: July 24, 2014
    Applicants: Korea Hydro And Nuclear Power Co., Ltd., Korea Atomic Energy Research Institute
    Inventors: Hui-Jun Won, Chong-Hun Jung, Sang Yoon Park, Wangkyu Choi, Jung-Sun Park, Jeikwon Moon, In-Ho Yoon, Byung-Seon Choi
  • Patent number: 8734597
    Abstract: Disclosed herein is a segmental ultrasonic cleaning apparatus configured to remove scales and/or sludge deposited on a tube sheet. The segmental ultrasonic cleaning apparatus includes a plurality of segment groups arranged in a ring shape on a top surface of a tube sheet along an inner wall of the steam generator, in which each of the segment groups includes an ultrasonic element segment and a guide rail support segment loosely connected to each other by metal wires through hand holes located at a lower portion of the steam generator, such that ultrasound waves radiated from an ultrasonic transducer in each of the ultrasonic element segments travels along the surface of the tube sheet, with the segment groups tightly connected in the ring shape by tightening the metal wires via wire pulleys of flange units.
    Type: Grant
    Filed: September 27, 2010
    Date of Patent: May 27, 2014
    Assignee: Korea Hydro & Nuclear Power Co., Ltd.
    Inventors: Seok Tae Kim, Woo Tae Jeong, Hee Geun Kim, Tae Young Kong
  • Patent number: 8705685
    Abstract: The geometric dimensions and shape of a device for removing solid particles from the cooling medium that is circulated in the primary circuit of a nuclear reactor, in particular a boiling water nuclear reactor, are such that the device can be inserted in lieu of a fuel element or fuel assembly into an empty fuel element or assembly position of the reactor core of the nuclear reactor.
    Type: Grant
    Filed: January 16, 2009
    Date of Patent: April 22, 2014
    Assignee: Areva GmbH
    Inventors: Hartmut Lelickens, Reazul Huq, Werner Meier, Jochen Heinecke
  • Patent number: 8548113
    Abstract: Example embodiments are directed to upper tie plates for debris mitigation and fuel bundles that use the upper tie plates. Example embodiment tie plates may include a plurality of debris capture elements that overlap each other so as to create debris traps for particulate debris that would fall onto the fuel bundle. Example embodiment fuel bundles may use the upper tie plates for debris mitigation.
    Type: Grant
    Filed: August 28, 2009
    Date of Patent: October 1, 2013
    Assignee: Global Nuclear Fuel - Americas, LLC
    Inventors: Michael T. Kiernan, Michael S. DeFilippis
  • Patent number: 8537960
    Abstract: Disclosed is an apparatus for performing an automated cleaning of nuclear fuel cladding-tubes. The apparatus comprises a pre-cleaning holding section disposed at a first side of the apparatus, a primary cleaning-material supplying section and a primary cleaning section disposed at a second side of the apparatus, a secondary cleaning section and a secondary cleaning material supplying section disposed at the second side of the apparatus and beside the primary cleaning section, an inspection section disposed at a third side of the apparatus that is opposite to the second side, and a post-cleaning holding section disposed at the fourth side of the transferring section. The pre-cleaning holding section and the post-cleaning holding section includes a cladding-tube guide where the cladding-tube is loaded before and after cleaning. Primary and secondary cleaning material supply sections are disposed at a lateral side of the primary and secondary cleaning sections respectively.
    Type: Grant
    Filed: December 22, 2009
    Date of Patent: September 17, 2013
    Assignee: Korea Nuclear Fuel Co., Ltd.
    Inventors: Ki-jun Kwon, Jeong-ho Kim, Se-yong Shin, Hung-soon Chang, Tae-hyung Na, Jong-sung Hong
  • Patent number: 8494107
    Abstract: A formic acid aqueous solution that contains Fe (II) ions is produced by dissolving metal iron in a formic acid aqueous solution. Nitrogen is supplied from a nitrogen supply device to a chemical liquid tank and then discharged from a discharge line to reduce the dissolved oxygen concentration in the aqueous solution. The chemical liquid tank is filled with the formic acid aqueous solution sealed with nitrogen, and is transferred from a factory to a nuclear reactor building designated as radiation-controlled areas. Inside the nuclear reactor building, the chemical liquid tank is installed in a film deposition apparatus connected to a reactor water recirculation pipeline. The formic acid aqueous is supplied from the chemical liquid tank to the inside of the reactor water recirculation pipeline, and then a ferrite film is formed on the inner surface of the reactor water recirculation pipeline.
    Type: Grant
    Filed: April 30, 2008
    Date of Patent: July 23, 2013
    Assignee: Hitachi, Ltd.
    Inventors: Hideyuki Hosokawa, Makoto Nagase, Satoshi Morisawa, Motoaki Sakashita, Katsuo Yokota
  • Patent number: 8457270
    Abstract: A method of suppressing deposition of radionuclides on components of a nuclear power plant comprises forming a ferrite film by contacting a first chemical including iron (II) ions, a second chemical for oxidizing the iron (II) ions to iron (III) ions, and a third chemical for adjusting the pH of a processing solution containing a mixture of the first and second chemicals to be 5.5 to 9.0 with the metal member surface in a time period from a finishing stage in decontamination step of removing contaminants formed on the surface of metal member composing the nuclear power plant, and suppressing deposition of radionuclides on the metal member by the ferrite film.
    Type: Grant
    Filed: January 4, 2011
    Date of Patent: June 4, 2013
    Assignee: Hitachi-GE Nuclear Energy, Ltd.
    Inventors: Hideyuki Hosokawa, Makoto Nagase, Kazushige Ishida, Yoichi Wada, Naoshi Usui, Motohiro Aizawa, Motomasa Fuse
  • Patent number: 8433030
    Abstract: Crystal habit modifiers (CHM) are provided to ameliorate deposit-related concerns in nuclear plant systems. The principal targets for utilization of crystal habit modifiers are Pressure Water Reactor (PWR) primary-side fuel rod crud and secondary-side steam generator deposits and Boiling Water Reactor (BWR) coolant system deposits.
    Type: Grant
    Filed: December 1, 2009
    Date of Patent: April 30, 2013
    Assignee: Electric Power Research Institute, Inc.
    Inventors: Keith Paul Fruzzetti, Karen Samie Kim, Robert Douglas Varrin, Jr., Charles Marks
  • Patent number: 8414685
    Abstract: The present invention relates to a system and method for removing dissolved gas from makeup water in a water-cooled nuclear reactor. The present invention includes a storage tank for containing the makeup water that includes the dissolved gas, a membrane system positioned downstream of the storage tank to at least partially remove the dissolved gas from the makeup water; and a transport mechanism to transfer the makeup water from an outlet of the membrane system for use in the water-cooled nuclear reactor. The dissolved gas can include at least one of dissolved oxygen, dissolved nitrogen, dissolved argon and mixtures thereof.
    Type: Grant
    Filed: September 8, 2010
    Date of Patent: April 9, 2013
    Assignee: Westinghouse Electric Company LLC
    Inventor: George G. Konopka
  • Publication number: 20130051508
    Abstract: Systems and methods for operating an accelerator driven sub-critical core. In one embodiment, a fission power generator includes a sub-critical core and a plurality of proton beam generators. Each of the proton beam generators is configured to concurrently provide a proton beam into a different area of the sub-critical core. Each proton beam scatters neutrons within the sub-critical core. The plurality of proton beam generators provides aggregate power to the sub-critical core, via the proton beams, to scatter neutrons sufficient to initiate fission in the sub-critical core.
    Type: Application
    Filed: August 31, 2011
    Publication date: February 28, 2013
    Applicant: TEXAS A&M UNIVERSITY SYSTEM
    Inventors: Peter M. MCINTYRE, Akhdiyor SATTAROV
  • Patent number: 8385497
    Abstract: A method to confine a nuclear reactor fuel bundle assembly including: inserting a lower portion of the fuel bundle assembly into an open end of a lower fuel particle barrier; supporting the lower portion of the fuel bundle with the lower fuel particle barrier; grasping the lower portion of the fuel bundle assembly with the lower fuel particle barrier; lowering an upper fuel particle barrier over an upper tie plate of the fuel bundle assembly; moving at least a portion of a handle fixed to the upper tie plate through an open slot in the upper fuel particle barrier; closing the open slot with a closure device after the handle passes through the slot, and preventing fuel particles being released from the nuclear reactor fuel bundle assembly by the upper and lower fuel particle barriers.
    Type: Grant
    Filed: December 29, 2011
    Date of Patent: February 26, 2013
    Assignee: Global Nuclear Fuel Americas, LLC
    Inventors: Paul Everett Cantonwine, Andrew K. Langston, Charles B. Patterson, Jr., Johnny R. Skipper, Alexander Michael Hay, Carlton Wayne Clark, David Grey Smith
  • Patent number: 8379789
    Abstract: This invention relates to a nuclear plant having a reactor vessel and a fluid circuit including flow path defining means, defining a flow path for circulating a reactor coolant fluid from and to the reactor vessel. The nuclear plant includes a particle collection zone defined along at least part of the length of the flow path, and particle deflection means arranged in particle deflecting relationship with the flow path to deflect particles from a fluid stream in the flow path into or toward the particle collection zone.
    Type: Grant
    Filed: July 27, 2011
    Date of Patent: February 19, 2013
    Assignee: Pebble Bed Modular Reactor (Proprietary) Limited
    Inventors: Leszek Andrzej Kuczynski, Francis Pieter Van Ravenswaay
  • Patent number: 8369473
    Abstract: A method for the surface tribological decontamination of nuclear fuel rods automates surface wiping by one or more bands of fabric. The band is distant from the axis of the rod, the rod is placed facing the band, and then the band is tensioned around the surface of the rod and moved. The rod may be immobile, moved in pure translation along its axis or with a wide-step helical movement. Preferably, the decontamination is carried by two bands simultaneously, so as to cover the total surface in one pass of the rod.
    Type: Grant
    Filed: December 7, 2006
    Date of Patent: February 5, 2013
    Assignee: Areva NC
    Inventors: Alain Dictor, Marc Fischer
  • Patent number: 8333893
    Abstract: A filtration separation method for waste resin containing highly radioactive uranium powder and device thereof is mainly used for the waste resin after water treatment process in a nuclear facility. The uranium powder contained in the waste resin is highly radioactive. Thus, prior to the treatment of the waste resin, it is necessary to filter and separate the highly radioactive uranium powder to reduce the radioactivity. It is to put the uranium powder containing waste resin into an underwater holding tank and withdraw the waste resin by an underwater pump into a uranium powder filtration box. Then the uranium powder filtration box is lifted by a hoist to move to an underwater ultrasonic cleaner. High-pressure water flushing is applied and followed by underwater ultrasonic cleaning. Then the cleaning water (containing precipitated uranium powder) from the ultrasonic cleaner is drained to uranium powder collection device.
    Type: Grant
    Filed: July 31, 2009
    Date of Patent: December 18, 2012
    Assignee: Institute of Nuclear Energy Research
    Inventors: Kuo-Yuan Chang, Ling-Huan Chiao, Chin-Teng Hsu, Chin-Chun Chu Ko, Bing-Rong Wu
  • Patent number: 8265221
    Abstract: A debris trap catches debris falling through a fuel bundle orifice in a nuclear reactor. The debris trap includes a shaft and a debris capture tray attached to an end of the shaft. The debris capture tray includes a tray cavity sized larger than the fuel bundle orifice.
    Type: Grant
    Filed: July 19, 2011
    Date of Patent: September 11, 2012
    Assignee: Global Nuclear Fuel—Americas, LLC
    Inventors: Steven Bruce Shelton, Gerald Martin Latter
  • Patent number: 8249211
    Abstract: Provided is a modified target assembly in which the target fluid is moved within the target assembly in a manner that increases the effective density of the target fluid within the beam path, thereby increasing beam yield utilizing forced convection. The target may also include optional structures, such as nozzles, diverters and deflectors for guiding and/or accelerating the flow of the target fluid. The target assembly directs the target fluid along an inner sleeve in a direction opposite the direction of the beam current to produce a counter current flow and may also direct the flow of the target fluid away from the inner surface of the inner sleeve and toward a central region in the target cavity. This countercurrent flow suppresses natural convection that tends to reduce the density of the target fluid in the beam path and tends to increase the heat transfer from the target.
    Type: Grant
    Filed: June 29, 2005
    Date of Patent: August 21, 2012
    Assignee: Advanced Applied Physics Solutions, Inc.
    Inventor: Kenneth Robert Buckley
  • Publication number: 20120183115
    Abstract: A method for the cleanup of ionic species such as cobalt and nickel in nuclear power plant aqueous streams using a sequestration resin material is disclosed herein. The method includes the steps of providing a sequestration resin for removal of radioisotopes of transition metal impurities contained in the plant process streams, and distributing the sequestration resin into the plant process streams such that the sequestration resin interacts with the process streams and removes the transition metal impurities.
    Type: Application
    Filed: November 23, 2011
    Publication date: July 19, 2012
    Applicant: ELECTRIC POWER RESEARCH INSTITUTE, INC.
    Inventors: Paul L. Frattini, Roger Howard Asay, Keith Paul Fruzzetti, Susan Elaine Garcia, Richard Herbert Kohlmann, Daniel Morgan Wells
  • Patent number: 8165261
    Abstract: A method for cleaning an irradiated nuclear fuel assembly includes chemically enhancing a technique utilizing an apparatus including a housing adapted to engage a nuclear fuel assembly. A set of ultrasonic transducers is positioned on the housing to supply radially emanating omnidirectional ultrasonic energy to remove deposits from the nuclear fuel assembly. Any corrosion products remaining after ultrasonic fuel cleaning will have exposed surfaces that are susceptible to chemical dissolution.
    Type: Grant
    Filed: January 6, 2009
    Date of Patent: April 24, 2012
    Assignee: Electric Power Research Institute, Inc.
    Inventors: Dennis Frank Hussey, Kurt Edsinger, Jeff Deshon
  • 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: 8069522
    Abstract: The invention provides a method and tool to perform an analysis of CRUD on a nuclear fuel rod. The method recites providing a nuclear fuel rod with a layer of CRUD on an exterior of the fuel rod, scraping the CRUD from the fuel rod with a CRUD scraping tool and collecting CRUD flakes from the CRUD scraping tool. The method also provides for sorting the CRUD flakes into particle fractions, and analyzing the CRUD with a scanning electron microscope, wherein the scraping tool has a blade with a rigidity that is matched to an anticipated CRUD deposit shear strength.
    Type: Grant
    Filed: October 18, 2007
    Date of Patent: December 6, 2011
    Assignee: AREVA NP Inc.
    Inventors: Mihai G. M. Pop, Brian G. Lockamon, Laurence S. Lamanna, John T. Willse
  • Publication number: 20110243293
    Abstract: Systems and methods for servicing a fuel assembly in a light water reactor include those for controlling flow through a fuel assembly to maintain debris in the fuel assembly during removal and transportation of the fuel assembly, those for discharging debris from the fuel assembly, and those for isolating and sampling the water chemistry of a fuel assembly. An exemplary system includes a closure device configured to seal a mast to a fuel assembly to surround the upper opening of the fuel assembly and provide a flow control channel between a void in the mast and a lower opening in a lower tie plate.
    Type: Application
    Filed: March 31, 2010
    Publication date: October 6, 2011
    Inventors: Peter Ray Diller, David Grey Smith, Michael T. Kiernan, Gerald A. Luciano, Colin F. Kelemen
  • Patent number: 8009790
    Abstract: A debris trap catches debris falling through a fuel bundle orifice in a nuclear reactor. The debris trap includes a shaft and a debris capture tray attached to an end of the shaft. The debris capture tray includes a tray cavity sized larger than the fuel bundle orifice.
    Type: Grant
    Filed: December 13, 2007
    Date of Patent: August 30, 2011
    Assignee: Global Nuclear Fuel — Americas, LLC
    Inventors: Steven Bruce Shelton, Gerald Martin Latter
  • Publication number: 20110122986
    Abstract: The present invention relates to a method and an apparatus for suppressing adhesion of a radioactive substance, capable of suppressing adhesion of the radioactive substance onto the surface of a metallic material forming a structural member in a nuclear plant. On the surface of the metallic material forming the structural member in a nuclear power generation plant, e.g., a surface 32A of a pipe 32, an adhesion-suppressing substance 34 containing titanium oxide as a titanium compound is disposed, and a part on which the adhesion-suppressing substance 34 has been formed, is held at 80° C. or higher. The adhesion-suppressing substance 34 is formed on the surface 32A of the pipe 32 by spraying a solution or a suspension liquid of the substance.
    Type: Application
    Filed: August 21, 2008
    Publication date: May 26, 2011
    Applicant: Kabushiki Kaisha Toshiba
    Inventors: Seiji Yamamoto, Masami Enda, Hiromi Aoi, Yutaka Uruma
  • Publication number: 20110116590
    Abstract: A method for the surface tribological decontamination of nuclear fuel rods automates surface wiping by one or more bands of fabric. The band is distant from the axis of the rod, the rod is placed facing the band, and then the band is tensioned around the surface of the rod and moved. The rod may be immobile, moved in pure translation along its axis or with a wide-step helical movement. Preferably, the decontamination is carried by two bands simultaneously, so as to cover the total surface in one pass of the rod.
    Type: Application
    Filed: December 7, 2006
    Publication date: May 19, 2011
    Applicant: Areva NC
    Inventors: Alain Dictor, Marc Fischer
  • Patent number: 7887767
    Abstract: The invention relates to a process for reprocessing a spent nuclear fuel and for preparing a mixed uranium-plutonium oxide, which process comprises: a) the separation of the uranium and plutonium from the fission products, the americium and the curium that are present in an aqueous nitric solution resulting from the dissolution of the fuel in nitric acid, this step including at least one operation of coextracting the uranium and plutonium from said solution by a solvent phase; b) the partition of the coextracted uranium and plutonium to a first aqueous phase containing plutonium and uranium, and a second aqueous phase containing uranium but no plutonium; c) the purification of the plutonium and uranium that are present in the first aqueous phase; and d) a step of coconverting the plutonium and uranium to a mixed uranium/plutonium oxide. Applications: reprocessing of nuclear fuels based on uranium oxide or on mixed uranium-plutonium oxide.
    Type: Grant
    Filed: May 24, 2007
    Date of Patent: February 15, 2011
    Assignees: Commissariat a l'Energie Atomique, Compagnie Generale des Matieres Nucleaires
    Inventors: Pascal Baron, Binh Dinh, Michel Masson, Francois Drain, Jean-Luc Emin
  • Publication number: 20110024704
    Abstract: Compositions are provided that include nuclear fuel. Methods for treating nuclear fuel are provided which can include exposing the fuel to a carbonate-peroxide solution. Methods can also include exposing the fuel to an ammonium solution. Methods for acquiring molybdenum from a uranium comprising material are provided.
    Type: Application
    Filed: July 29, 2009
    Publication date: February 3, 2011
    Inventors: Chuck Z. Soderquist, Amanda M. Johnsen, Bruce K. McNamara, Brady D. Hanson, Steven C. Smith, Shane M. Peper
  • Patent number: 7811392
    Abstract: It is an object of the present invention to efficiently suppress radionuclide deposition on a reactor component of nuclear power plant. Radionuclide deposition on the surface of a metallic reactor component of nuclear power plant is suppressed by forming a ferrite film on the component, wherein the film is formed, after decontamination for removing radionuclides contaminants from the component surface is completed and before the plant is started up, by contacting a treatment solution which mixes a first agent containing the iron (II) ions, a second agent for oxidizing the iron (II) ions into the iron (III) ions and a third agent for adjusting pH level of a solution to 5.5 to 9.0 in this order with the reactor component surface.
    Type: Grant
    Filed: July 14, 2006
    Date of Patent: October 12, 2010
    Assignee: Hitachi-GE Nuclear Energy, Ltd.
    Inventors: Hideyuki Hosokawa, Makoto Nagase, Kazushige Ishida, Youichi Wada, Naoshi Usui, Motohiro Aizawa, Motomasa Fuse
  • 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
  • Patent number: 7776223
    Abstract: This present invention is related to a method of collecting high-level radioactive contaminated uranium powder underwater. It utilizes a long rod fixed to the pipe of the sewage pump at bottom, and takes another end of the sewage pump to connect to the sediment bag to collect uranium powder which is dispersed and contaminates the pond. Inhaling the pond water contains uranium powder into the sediment bag by sewage pump that is joined to a collecting can under it and waiting for precipitation of the powder. When the uranium powder in the sediment bag is completely precipitated into the collecting can, operator can utilize submersible pump to drain the pond water from the sediment bag. Operator may hold the cable wire of the uranium powder collecting can manually to move it to the collecting shelf and repeat the process several times until the high-level radioactive uranium powder in the contaminated pond are all collected on the uranium powder collecting shelf.
    Type: Grant
    Filed: July 15, 2008
    Date of Patent: August 17, 2010
    Assignee: Institute of Nuclear Energy Research
    Inventors: Kuo-Yung Chang, Heng-Shiung Shen, Li Ma, Chung-Sheng Chen, Tsu-Man Chen
  • Publication number: 20100195783
    Abstract: Disclosed is an apparatus for performing an automated cleaning of nuclear fuel cladding-tubes. The apparatus comprises a pre-cleaning holding section disposed at a first side of the apparatus, a primary cleaning-material supplying section and a primary cleaning section disposed at a second side of the apparatus, a secondary cleaning section and a secondary cleaning material supplying section disposed at the second side of the apparatus and beside the primary cleaning section, an inspection section disposed at a third side of the apparatus that is opposite to the second side, and a post-cleaning holding section disposed at the fourth side of the transferring section. The pre-cleaning holding section and the post-cleaning holding section includes a cladding-tube guide where the cladding-tube is loaded before and after cleaning. Primary and secondary cleaning material supply sections are disposed at a lateral side of the primary and secondary cleaning sections respectively.
    Type: Application
    Filed: December 22, 2009
    Publication date: August 5, 2010
    Applicant: KOREA NUCLEAR FUEL CO., LTD.
    Inventors: Ki-jun KWON, Jeong-ho KIM, Se-yong SHIN, Hung-soon CHANG, Tae-hyung NA, Jong-sung HONG
  • Patent number: 7542539
    Abstract: An apparatus for cleaning an irradiated nuclear fuel assembly includes a housing adapted to engage a nuclear fuel assembly. A set of ultrasonic transducers is positioned on the housing to supply radially emanating omnidirectional ultrasonic energy to remove deposits from the nuclear fuel assembly.
    Type: Grant
    Filed: December 10, 2001
    Date of Patent: June 2, 2009
    Assignee: Electric Power Research Institute, Inc.
    Inventors: Paul L. Frattini, Robert Douglas Varrin, Edwin Stephen Hunt
  • Publication number: 20090003509
    Abstract: A method of suppressing deposition of radionuclides on components of a nuclear power plant comprises forming a ferrite film by contacting a first chemical including iron (II) ions, a second chemical for oxidizing the iron (II) ions to iron (III) ions, and a third chemical for adjusting the pH of a processing solution containing a mixture of the first and second chemicals to be 5.5 to 9.0 with the metal member surface in a time period from a finishing stage in decontamination step of removing contaminants formed on the surface of metal member composing the nuclear power plant, and suppressing deposition of radionuclides on the metal member by the ferrite film.
    Type: Application
    Filed: July 1, 2008
    Publication date: January 1, 2009
    Applicant: Hitachi-GE NUCLEAR ENERGY, LTD.
    Inventors: Hideyuki Hosokawa, Makoto Nagase, Kazushige Ishida, Yoichi Wada, Naoshi Usui, Motohiro Aizawa, Motomasa Fuse
  • Publication number: 20080101527
    Abstract: The present invention provides a method for removing niobium-rich second-phase-particle (SPP) deposits from zirconium-niobium alloy components. The method comprises washing a freshly pickled and rinsed zirconium-niobium alloy component with an acidified oxalic acid or ammonium oxalate washing solution. The method of the present invention results in a rapid, efficient and complete removal of surface SPP deposits from the zirconium-niobium alloy component without pitting, leaving behind a clean, shiny surface without the need to use water blasting or mechanical wiping operations.
    Type: Application
    Filed: March 7, 2007
    Publication date: May 1, 2008
    Inventor: David F. McLaughlin
  • Patent number: 7304301
    Abstract: The invention provides a method and tool to perform an analysis of CRUD on a nuclear fuel rod. The method recites providing a nuclear fuel rod with a layer of CRUD on an exterior of the fuel rod, scraping the CRUD from the fuel rod with a CRUD scraping tool and collecting CRUD flakes from the CRUD scraping tool. The method also provides for sorting the CRUD flakes into particle fractions, and analyzing the CRUD with a scanning electron microscope, wherein the scraping tool has a blade with a rigidity that is matched to an anticipated CRUD deposit shear strength.
    Type: Grant
    Filed: September 18, 2006
    Date of Patent: December 4, 2007
    Assignee: Framatome ANP, Inc.
    Inventors: Mihai G. M. Pop, Brian G. Lockamon, Laurence S. Lamanna, John T. Willse
  • Patent number: 7149272
    Abstract: The invention refers to a filter (1) for separating particle from cooling water in a nuclear plant, and a fuel assembly with such a filter. The filter has an inlet end (2) and an outlet end (3) and permits through-flow of the cooling water in a main flow direction (x). The filter includes a number of sheets (4) extending in the flow direction from the inlet end to the outlet end. The sheets are arranged beside each other and form passages for the cooling water. The sheets include a first portion (4?) extending from the inlet end (2), a second portion (4?) extending from the outlet end (3), and a third portion (4??) extending between the first portion (4?) and the second portion (4?). The sheets (4) have along the first portion continuous wave-shape extending in a direction (y) transversally to the flow direction (x) and along the third portion a continuous wave-shape extending in the flow direction (x).
    Type: Grant
    Filed: January 21, 2002
    Date of Patent: December 12, 2006
    Assignee: Westinghouse Electric AB Sweden
    Inventors: Anders Söderlund, Håkan Söderberg
  • Patent number: 6973154
    Abstract: In a chemical decontamination method of chemically decontaminating radioactive nuclides from a metallic material, oxalic acid and hydrazine are injected as a reductive decontaminating agent into water that is in contact with the metallic material. Injection of the hydrazine is stopped after a cation resin arranged in a circulation line connected to the metallic material breaks, and at least the oxalic acid and the hydrazine in the reductive decontaminating agent are decomposed using a decomposing catalyst.
    Type: Grant
    Filed: December 4, 2001
    Date of Patent: December 6, 2005
    Assignees: Hitachi, Ltd., Kurita Engineering Co., Ltd.
    Inventors: Makoto Nagase, Naohito Uetake, Kazushige Ishida, Fumito Nakamura, Kazumi Anazawa, Tadashi Tamagawa, Hiroo Yoshikawa
  • Patent number: 6972095
    Abstract: A decontamination system uses magnetic molecules having ferritin cores to selectively remove target contaminant ions from a solution. The magnetic molecules are based upon a ferritin protein structure and have a very small magnetic ferritin core and a selective ion exchange function attached to its surface. Various types of ion exchange functions can be attached to the magnetic molecules, each of which is designed to remove a specific contaminant such as radioactive ions. The ion exchange functions allow the magnetic molecules to selectively absorb the contaminant ions from a solution while being inert to other non-target ions. The magnetic properties of the magnetic molecule allow the magnetic molecules and the absorbed contaminant ions to be removed from solution by magnetic filtration.
    Type: Grant
    Filed: May 7, 2003
    Date of Patent: December 6, 2005
    Assignee: Electric Power Research Institute
    Inventors: Sean P. Bushart, David Bradbury, George Richard Elder
  • Patent number: 6950489
    Abstract: The invention relates to a guide tube especially for an instrumentation lance extending into a reactor pressure vessel. The guide tube includes a lower tube section and an upper tube section that extends into the interior of the reactor pressure vessel. In order to prevent radioactively contaminated particles from reaching the lower tube section disposed outside the reactor pressure vessel from forming a source of radiation, a separator is arranged in the upper tube section. The separator has a separation chamber in which the particles are deposited and are removed from the water.
    Type: Grant
    Filed: September 9, 2003
    Date of Patent: September 27, 2005
    Assignee: Framatome ANP GmbH
    Inventor: Gerhard Zuch
  • Patent number: 6944254
    Abstract: A reactor coolant system of a pressurized water nuclear reactor with fuel assemblies in the core is simultaneously shutdown and decontaminated in less than 90 hours after the shutdown is initiated. A LOMI or Can-Derem decontamination reagent is added to reactor coolant to reduce iron and nickel in oxidized coatings before removing dissolved hydrogen and reducing the gamma emitting activity of the reactor coolant.
    Type: Grant
    Filed: July 30, 2003
    Date of Patent: September 13, 2005
    Assignee: Westinghouse Electric Co., LLC
    Inventors: Joseph W. Kormuth, William A. Byers, Richard D. Reid, George P. Sabol
  • Patent number: 6928134
    Abstract: An apparatus admits gas into the primary coolant of a pressurized water nuclear reactor having a coolant loop for a liquid coolant, in particular water, to which hydrogen is to be added. The coolant loop preferably includes a volume control tank for the coolant as well as at least one high-pressure pump which admits coolant that has been extracted from the coolant loop back into the coolant loop again. An admission point for the hydrogen is located in a suction line on the suction side of the high-pressure pump. A measurement line on the pressure side of the high-pressure pump communicates with the volume control tank or with a dewatering system. A device for measuring the hydrogen content in the coolant is incorporated into the measurement line. The measuring device is connected through a control device to a control valve, with which the delivery of hydrogen to the admission point can be controlled. The gas admission apparatus assures a definite, precisely maintained hydrogen content in the coolant.
    Type: Grant
    Filed: March 30, 1998
    Date of Patent: August 9, 2005
    Assignee: Framatome ANP GmbH
    Inventors: Anwer Puthawala, Helmut Stünkel
  • Patent number: 6921515
    Abstract: In a chemical decontamination apparatus, a catalyst decomposition column in an upstream side of an ion exchange resin column and a hydrogen peroxide injection apparatus in a further upstream side, reduce the amount of waste products caused by a chemical decontaminating agent where a mixed decontaminating agent for a composition trapped in a cation resin column and for a composition trapped in an anion exchange resin are used for the chemical decontaminating agent, selectively decompose the composition trapped in the cation resin column in an inlet side of a cleaning apparatus when radioactive nuclides in the decontaminating agent are cleansed using the cation resin column during decontamination, and decompose both compositions after completion of the decontamination. The chemical decontamination thus selectively decomposes the chemical decontaminating agent, which is a component of the load to the cation resin column.
    Type: Grant
    Filed: December 4, 2001
    Date of Patent: July 26, 2005
    Assignees: Hitachi, Ltd., Kurita Engineering Co., Ltd.
    Inventors: Makoto Nagase, Naohito Uetake, Kazushige Ishida, Fumito Nakamura, Kazumi Anazawa, Tadashi Tamagawa, Hiroo Yoshikawa
  • Patent number: 6907891
    Abstract: A radioactive substance decontamination method and apparatus which decontaminates a metal member contaminated by radioactive substance in a short period of time. This apparatus has (1) multiple reducing decontamination tanks having different radiation control values; (2) a carrier for immersing the metal member into the multiple reducing decontamination tanks and a washing tank; (3) a tube for transferring into the second reducing decontamination tank the reducing decontamination agent in the first reducing decontamination tank; (4) a reducing agent decomposer for decomposing a component contained in the reducing decontamination agent of the reducing decontamination tank where the radiation control value is the highest out of the reducing decontamination tanks connected by the tube; and (5) a washing tank for washing the reducing decontamination agent deposited on the decontaminated metal member.
    Type: Grant
    Filed: February 21, 2002
    Date of Patent: June 21, 2005
    Assignees: Hitachi, Ltd., Hitachi Engineering Co., Ltd.
    Inventors: Kazumi Anazawa, Motoaki Sakashita, Makoto Nagase