Pressure Suppression And Relief Patents (Class 376/283)
  • Patent number: 10726959
    Abstract: When a power source is lost after an operation stop of a nuclear power plant, a first open/close valve is opened via a first battery at an early stage and steam in a reactor pressure vessel (RPV) is condensed in a suppression pool. The heat of the water in the suppression pool is transmitted to a cooling water pool located below inner space between first and second reactor containment vessels surrounding the RPV. A second open/close valve is opened via a second battery at the early stage and cooling water in a tank is injected into the RPV. After the early stage, a third open/close valve is opened via a third battery, and a cooling medium becomes steam by an evaporator in the RPV, the steam being condensed by a condenser disposed in the inner space to become a liquid of the cooling medium and is returned to the evaporator.
    Type: Grant
    Filed: April 14, 2016
    Date of Patent: July 28, 2020
    Assignee: Hitachi-GE Nuclear Energy, Ltd.
    Inventors: Kenichi Katono, Masao Chaki, Kazuaki Kito
  • Patent number: 10720248
    Abstract: In a pressurized water reactor (PWR), emergency core cooling (ECC) responds to depressurization due to a vessel penetration break at the top of the pressure vessel by draining water from a body of water through an injection line into the pressure vessel. A barrier operates concurrently with the ECC to suppress flow of liquid water from the pressure vessel out the vessel penetration break. The barrier may comprise one or more of: (1) an injection line extension passing through the central riser to drain water into the central riser; (2) openings in a lower portion of a central riser to shunt some upward flow from the central riser into a lower portion of the downcomer annulus; and (3) a surge line providing fluid communication between a pressurizer volume at the top of the pressure vessel and the remainder of the pressure vessel which directs water outboard toward the downcomer annulus.
    Type: Grant
    Filed: March 17, 2014
    Date of Patent: July 21, 2020
    Assignee: BWXT mPower, Inc.
    Inventors: John D. Malloy, III, Billy E. Bingham, Ronald C. Watson, Jason G. Williams, Matthew W. Ales, James B. Inman, Sean M. Boyle
  • Patent number: 10522256
    Abstract: A nuclear reactor chamber comprises an inlet portion. The chamber is a part of a nuclear power plant. At least one container contains liquid nitrogen and cold nitrogen vapor and includes an outlet portion. At least one thermally activated release mechanism is respectively connected between one of the at least one container and the inlet portion. Each thermally activated release mechanism is configured to release the liquid nitrogen from a connected container into the inlet portion when a predetermined safety threshold temperature is reached, so that the released liquid nitrogen produces an expanding volume of cold nitrogen vapor within the nuclear reactor chamber.
    Type: Grant
    Filed: December 15, 2017
    Date of Patent: December 31, 2019
    Inventor: Catherine Lin-Hendel
  • Patent number: 10438707
    Abstract: An atomic power plant is provided including a primary containment vessel (PCV) 1, a reactor pressure vessel (RPV) 3, a main steam line 4, two steam safety relief valves (SRVs) 6, a pressure suppression pool (S/P) 8, an SRV exhaust pipe 9 which is connected to a quencher 10, a temperature measuring instrument 12 which measures a temperature inside the quencher 10, an SRV controller 13 which controls opening and closing of the SRVs 6. After a lapse of predetermined time from when the SRV 6 is opened, in a case where it is determined that a temperature detected by the temperature measuring instrument 12 is equal to or smaller than a predetermined threshold value, the SRV controller 13 causes the SRV 6 to which the temperature measuring instrument 12 detecting the temperature leads, to be closed and to be prohibited from being opened.
    Type: Grant
    Filed: January 31, 2017
    Date of Patent: October 8, 2019
    Assignee: Hitachi-GE Nuclear Energy, Ltd.
    Inventors: Kazuaki Kito, Takahisa Matsuzaki, Tomohiko Ikegawa
  • Patent number: 10325688
    Abstract: The present invention relates to a passive heat removal system which circulates cooling fluid to a steam generator via a main water supply line connected to the lower inlet of the steam generator, and a main steam pipe connected to the top outlet of the steam generator, to remove sensible heat of a nuclear reactor coolant system and residual heat of a core. The heat removal system comprises supplementary equipment for receiving surplus cooling fluid or for supplying supplementary cooling fluid in order to maintain the flow rate of the cooling fluid within a predetermined range. The supplementary equipment comprises: a supplementary tank, installed at a height between the lower inlet and the top outlet of the steam generator; a first connection pipe, connected to the main steam pipe and the supplementary tank; and a second connection pipe, connected to the supplementary tank and the main water supply pipe.
    Type: Grant
    Filed: July 22, 2015
    Date of Patent: June 18, 2019
    Assignee: KOREA ATOMIC ENERGY RESEARCH INSTITUTE
    Inventors: Young In Kim, Keung Koo Kim, Ju Hyeon Yoon, Jae Joo Ha, Tae Wan Kim, Cheon Tae Park, Seung Yeob Ryu, Han Ok Kang, Young Min Bae, Joo Hyung Moon, Hun Sik Han, Kyung Jun Kang, Soo Jai Shin, Seo Yoon Jung, Young Soo Kim
  • Patent number: 10290379
    Abstract: A passive containment cooling and filtered venting system includes: an outer well; a scrubbing pool arranged in the outer well; a cooling water pool installed above the dry well and the outer well; a heat exchanger partly submerged in the cooling water; a gas supply pipe that is connected to the inlet plenum of the ruin of the heat exchanger at one end and connected to a gas phase region of the containment vessel at the other end; a condensate return pipe that is connected to the outlet plenum of the heat exchanger at one end, and connected to inside the containment vessel at other end; and a gas vent pipe that is connected to the outlet plenum of the heat exchanger at one end and is submerged in the scrubbing pool at other end.
    Type: Grant
    Filed: July 2, 2015
    Date of Patent: May 14, 2019
    Assignee: Kabushiki Kaisha Toshiba
    Inventors: Takashi Sato, Keiji Matsumoto
  • Patent number: 10236085
    Abstract: A pressure-relief system for the containment of a nuclear power facility allows reliable operation of a wet scrubber for the pressure relief flow with a simultaneously compact structural design. The pressure relief system has a pressure relief line guided through the containment and can be closed by a shut-off valve, a wet scrubber arranged in a portion of the pressure relief line located inside the containment, for the pressure relief flow which forms in the pressure-relief mode when the shut-off valve is open, a reservoir arranged inside the containment and is fluidically connected to the remaining inner space of the containment such that any overpressure, with respect to the surroundings outside the containment, prevailing in the containment is transferred at least in part to the reservoir, and a supply line leading from the reservoir to the wet scrubber for supplying the wet scrubber with fluid from the reservoir.
    Type: Grant
    Filed: September 28, 2015
    Date of Patent: March 19, 2019
    Assignee: Framatome GmbH
    Inventors: Bernd Eckardt, Norbert Losch, Frank Zehe
  • Patent number: 10062462
    Abstract: The present invention provides a facility for reducing radioactive material comprising: a cooling water storage unit installed inside a containment and formed to store cooling water; a boundary unit forming a boundary of radioactive material inside the containment and surrounding a reactor coolant system installed inside the containment to prevent a radioactive material from releasing from the reactor coolant system or a pipe connected with the reactor coolant system to the containment; a connecting pipe connected with an inner space of the boundary unit and the cooling water storage unit to guide a flow of a fluid caused by a pressure difference between the boundary unit and the cooling water storage unit from the boundary unit to the cooling water storage unit; and a sparging unit disposed to be submerged in the cooling water stored in the cooling water storage unit and connected with the connecting pipe to sparge the fluid that has passed through the connecting pipe and the radioactive material contained i
    Type: Grant
    Filed: August 26, 2014
    Date of Patent: August 28, 2018
    Assignee: KOREA ATOMIC ENERGY RESEARCH INSTITUTE
    Inventors: Young In Kim, Kyung Jun Kang, Keung Koo Kim, Hun Sik Han, Ju Hyeon Yoon, Jae Joo Ha, Dae Hyun Hwang, Suhn Choi, Joo Hyung Moon, Soo Jai Shin
  • Patent number: 10014082
    Abstract: A nuclear power plant according to an embodiment comprises: a reactor well; a reactor well upper lid; an operation floor; an operation floor area wall; a standby gas treatment system; and a reactor well exhaust section to release the gas inside the reactor well to the environment without releasing the gas into the operation floor area in an event of a predetermined accident, e.g., causing diminished cooling of a containment vessel or otherwise increasing its temperature. The standby gas treatment system includes: a suction pipe to take in gas inside the reactor building; an exhaust fan; a standby gas treatment system exhaust pipe; a heater that is disposed between the suction pipe and the standby gas treatment system exhaust pipe; and a filter to filter the gas heated by the heater and to send the gas to the standby gas treatment system exhaust pipe.
    Type: Grant
    Filed: May 21, 2015
    Date of Patent: July 3, 2018
    Assignee: Kabushiki Kaisha Toshiba
    Inventors: Takashi Sato, Keiji Matsumoto
  • Patent number: 9997264
    Abstract: In accordance with the present invention, there is provided a strainer system for use in a nuclear sump. The strainer system of the present invention includes at least one primary strainer module which defines a primary strainer/filter surface. In the strainer system, the primary strainer surface of the primary strainer module has a debris interceptor which is cooperatively engaged thereto, and may be outfitted with one or more pressure released or activated membranes. In a loss of coolant accident, the debris interceptor, alone or in combination with the pressure activated membrane(s), is adapted to reduce the differential pressure experienced across the strainer system in nuclear power plants with medium to high fiber loads.
    Type: Grant
    Filed: February 14, 2012
    Date of Patent: June 12, 2018
    Assignee: Control Components, Inc.
    Inventors: Carl Prather, Denis Grob, Claes Lemcke
  • Patent number: 9864823
    Abstract: A cleansing system for improving operation of a petrochemical plant or refinery. The petrochemical plant or refinery may include a fractionation column, a condenser, and a pump. Equipment, such as condensers, receivers, reboilers, feed exchangerss, and pumps may be divided into subsections. Temperatures, pressures, flows, and other plant operations may be used for optimizing plant performance. A cleansing unit performs an enhanced cleansing process, which may allow early detection and diagnosis of the plant operating conditions based on one or more environmental factors.
    Type: Grant
    Filed: July 24, 2017
    Date of Patent: January 9, 2018
    Assignee: UOP LLC
    Inventors: Ian G. Horn, Christophe Romatier, Paul Kowalczyk, Zak Alzein
  • Patent number: 9786394
    Abstract: A component cooling water system for a nuclear power plant. In one embodiment, the system includes an inner containment vessel housing a nuclear reactor and an outer containment enclosure structure. An annular water reservoir is formed between the containment vessel and containment enclosure structure which provides a heat sink for dissipating thermal energy. A shell-less heat exchanger is provided having an exposed tube bundle immersed in water held within the annular water reservoir. Component cooling water from the plant flows through the tube bundle and is cooled by transferring heat to the annular water reservoir. In one non-limiting embodiment, the tube bundle may be U-shaped.
    Type: Grant
    Filed: August 21, 2013
    Date of Patent: October 10, 2017
    Inventors: Krishna P. Singh, Joseph Rajkumar
  • Patent number: 9697914
    Abstract: According to an embodiment, a nuclear power plant has a core; a reactor pressure vessel; a dry well; a wet well; a vacuum breaker; a containment vessel including the dry well, the LOCA vent pipe, the wet well, and the vacuum breaker; a cooling water pool placed outside the containment vessel; a heat exchanger at least partially submerged in cooling water; a gas supply pipe connected to the inlet plenum of the heat exchanger and the dry well; a condensate return pipe connected to the outlet plenum of the heat exchanger and the containment vessel; and a gas vent pipe connected to the outlet plenum of the heat exchanger and an outside of the wet well so that non-condensable gas inside the heat exchanger is released out of the wet well. The gas vent pipe is not connected to the wet well.
    Type: Grant
    Filed: June 19, 2013
    Date of Patent: July 4, 2017
    Assignee: Kabushiki Kaisha Toshiba
    Inventors: Takashi Sato, Keiji Matsumoto
  • Patent number: 9502142
    Abstract: A containment for a water cooled and moderated nuclear reactor incorporates two or more separate containment zones. These zones are constructed in such a manner that a leak or break in the reactor coolant system located within one zone will remain confined within this particular zone, so that no adverse ambient conditions of pressure, temperature, and humidity will propagate to any of the other zones. The separation between zones is achieved by having a partition plate extending between the containment envelope and the reactor coolant system where the partition plate is attached to one of the main components of the reactor coolant system. For example, this can be the reactor pressure vessel, as shown in some of the embodiments. The partition is designed to the same pressure and temperature conditions as the containment vessel envelope to ensure a leak tight and permanent separation between adjacent zones.
    Type: Grant
    Filed: July 17, 2014
    Date of Patent: November 22, 2016
    Inventor: Nico M. Bonhomme
  • Patent number: 9396821
    Abstract: A safety system for a nuclear plant includes a plurality of catalytic recombiner elements each triggering a recombination reaction with oxygen when hydrogen is entrained in an onflowing gas flow, so that reliable elimination of the hydrogen from the gas mixture is ensured with an especially high degree of operational safety even based on comparatively extreme conditions or scenarios of the aforementioned type. The recombiner elements and/or the flow paths each connecting two recombiner elements on the gas side are configured in such a way that a pressure pulse triggered in the gas medium by an ignition during the recombination reaction in a first recombiner element triggers a gas displacement process having a flow rate of at least 5 m/s in the onflow region of a second, adjacent recombiner element. A nuclear plant with a safety system is also provided.
    Type: Grant
    Filed: June 11, 2010
    Date of Patent: July 19, 2016
    Assignee: Areva GmbH
    Inventors: Bernd Eckardt, Norbert Losch
  • Patent number: 9194629
    Abstract: A condensation chamber cooling system of a condensation chamber for a boiling water reactor has a heat exchanger outside the condensation chamber. An elongate cooling module is provided in the condensation chamber with an evaporation space in its upper region. The cooling module is configured such that the evaporation space is located above a maximum filling level of the condensation chamber. The cooling module includes at least one riser pipe and one downpipe that issue with their upper ends into the evaporation space and with their lower ends in the condensation chamber. A first pressure line leads from the evaporation space to the heat exchanger and, from there, a second pressure line which issues in the condensation chamber below the minimum filling level. Thus, the condensation chamber, the pressure lines, the cooling module and the heat exchanger form a passive closed cooling circuit.
    Type: Grant
    Filed: September 28, 2012
    Date of Patent: November 24, 2015
    Assignee: WESTINGHOUSE ELECTRIC GERMANY GMBH
    Inventors: Wolfgang Tietsch, Daniel Freis, Felix Sassen
  • Publication number: 20150117586
    Abstract: In conjunction with a pressurized water reactor (PWR) and a pressurizer configured to control pressure in the reactor pressure vessel, a decay heat removal system comprises a pressurized passive condenser, a turbine-driven pump connected to suction water from at least one water source into the reactor pressure vessel; and steam piping configured to deliver steam from the pressurizer to the turbine to operate the pump and to discharge the delivered steam into the pressurized passive condenser. The pump and turbine may be mounted on a common shaft via which the turbine drives the pump. The at least one water source may include a refueling water storage tank (RWST) and/or the pressurized passive condenser. A pressurizer power operated relief valve may control discharge of a portion of the delivered steam bypassing the turbine into the pressurized passive condenser to control pressure in the pressurizer.
    Type: Application
    Filed: October 28, 2013
    Publication date: April 30, 2015
    Inventor: Thomas G. Graham
  • Publication number: 20140301524
    Abstract: The underwater electricity production module according to the invention includes means in the form of an elongated cylindrical box (12) in which means are integrated forming an electricity production unit including means forming a nuclear boiler (30), associated with electricity production means (37) connected to an external electricity distribution station by electrical cables, is characterized in that the nuclear boiler-forming means (30) are placed in a dry chamber (19) of the reactor compartment (18) associated with the chamber forming a safety water storage reservoir (20) of the reactor whereof at least the radial wall (53) is in a heat exchange relationship with the marine environment and in that the dry compartment (19) of the reactor container (18) is connected to the safety water storage reservoir chamber (20) of the reactor by depressurizing means (70) including means (71) forming a depressurizing valve placed in the upper portion of the dry chamber (19) and connected to one of the bubbler-forming m
    Type: Application
    Filed: January 18, 2013
    Publication date: October 9, 2014
    Inventor: Geoffrey Haratyk
  • Patent number: 8848854
    Abstract: The present invention relates to an alternate feedwater injection system to at least partially mitigate the effects of an aircraft impact on a light water nuclear reactor positioned in a reactor building. The light water nuclear reactor has a primary system and a reactor core. The alternate feedwater injection system includes a water storage tank, an injection point into the primary system, a pump capable to transfer water from the water storage tank to the injection point and ultimately to the reactor core. The water storage tank and pump are located external to a reactor building and outside of an identified aircraft impact area or inside the identified aircraft impact area and provided with a means of protection from the aircraft impact.
    Type: Grant
    Filed: September 24, 2010
    Date of Patent: September 30, 2014
    Assignee: Westinghouse Electric Company LLC
    Inventors: Nirmal Jain, James R. Nowell, Subhash Chandra, Edward E. Berry
  • Publication number: 20140254738
    Abstract: The present invention is directed to remote operation of an operation valve such as an air operated valve even at the time of power loss. A gas supply apparatus of the present invention includes: an operation valve mounted in some midpoint of a piping for passing at least gas in a plant and operating a valve body by the gas flowing in the piping; an solenoid valve mounted in some midpoint of the piping and allowing/stopping flow of the gas to the operation valve; and a gas supply source for supplying gas to the solenoid valve. A switching valve for switching between exhaust from the solenoid valve and gas supply to the solenoid valve is mounted in an exhaust line of the solenoid valve and, at the time of power loss, the switching valve is switched to connection to the gas supply source for supplying gas to the solenoid valve.
    Type: Application
    Filed: February 19, 2014
    Publication date: September 11, 2014
    Applicant: HITACHI-GE NUCLEAR ENERGY, LTD.
    Inventors: Ryo KUBOTA, Kenji ONODERA, Yoshihisa KIYOTOKI
  • Publication number: 20140241484
    Abstract: A passive cooling system of a pressurized water reactor that relies on a depressurization system to reduce the pressure in the reactor vessel in the event of a loss of coolant accident and vent the steam generated by the decay heat of the reactor core in a post loss of coolant accident stage. The depressurization results in a low pressure difference between the reactor vessel and the containment and enables gravity driven cooling system injection into the reactor vessel. The depressurization system includes a flow restrictor within an orifice in the reactor vessel wall that connects to a vent pipe which forms a flow path between the interior of the reactor vessel and the containment atmosphere when a valve within the vent pipe is in an open position. Preferably, the flow restrictor is a venturi that has a gradual contraction and a gradual expansion in the flow path area.
    Type: Application
    Filed: February 27, 2013
    Publication date: August 28, 2014
    Applicant: Westinghouse Electric Company LLC
    Inventors: Jun Liao, Vefa N. Kucukboyaci
  • Publication number: 20140233688
    Abstract: A power module assembly includes a reactor core immersed in a coolant and a reactor vessel housing the coolant and the reactor core. An internal dry containment vessel submerged in liquid substantially surrounds the reactor vessel in a gaseous environment. During an over-pressurization event the reactor vessel is configured to release the coolant into the containment vessel and remove a decay heat of the reactor core through condensation of the coolant on an inner surface of the containment vessel.
    Type: Application
    Filed: July 31, 2012
    Publication date: August 21, 2014
    Applicant: The State of OR acting by through the State Board of Higher Education on behalf of OR State Univ.
    Inventors: Jose N. REYES, JR., John T. Groome
  • Publication number: 20140226779
    Abstract: According to an embodiment, a reactor pressure vessel depressurization system has: a main steam safety relief valve, a main steam safety relief valve driving gas pipe; a three-way solenoid valve having the first connection port; a driving gas feed pipe connected to the second connection port; and a containment vessel external connection pipe connected to the third connection port and extending to outside of the reactor containment vessel. The three-way solenoid valve is either in the first communication state where the first connection port communicates with the second connection port or in the second communication state where the first connection port communicates with the third communication port. The containment vessel external connection pipe has an open communication section open in normal operation and capable of being unopened, and an external gas receiving section capable of receiving second driving gas.
    Type: Application
    Filed: February 4, 2014
    Publication date: August 14, 2014
    Applicant: Kabushiki Kaisha Toshiba
    Inventors: Ryohei SATO, Koji Nishino, Takeshi Tokunaga, Yasutaka Aoki, Takashi Sato
  • Patent number: 8804896
    Abstract: A method and a device depressurize a nuclear power plant. A depressurization flow is conducted out of a containment shell into the atmosphere via a depressurization line having a filter system. The filter system contains a filter chamber having an inlet, an outlet, and a sorbent filter. The depressurization flow is first conducted in a high-pressure section, then is depressurized by expansion at a throttle device, then conducted through the filter chamber having the sorbent filter, and finally blown out. To enable an effective retention of activity carriers contained in the depressurization flow, including organic compounds containing iodine, the depressurization flow depressurized by the throttle device is conducted through a superheating section before the depressurization flow enters the filter chamber, in which superheating section the depressurization flow is heated from the not yet depressurized depressurization flow to a temperature that is at least 10° C. above the dew point temperature.
    Type: Grant
    Filed: February 25, 2013
    Date of Patent: August 12, 2014
    Assignee: Areva GmbH
    Inventors: Bernd Eckardt, Norbert Losch, Carsten Pasler
  • Publication number: 20140185729
    Abstract: A system and a method for a passive containment vent system for a Boiling Water Reactor (BWR). The system is capable of venting and scrubbing a gaseous discharge from the primary containment of the BWR over a prolonged period of time leading up to or following a serious plant accident, without the need for monitoring by on-site plant personnel. External electrical power is not required (following initial activation of the system) in order to operate the containment vent system. The system may protect the integrity of primary containment during and following the serious plant accident.
    Type: Application
    Filed: December 28, 2012
    Publication date: July 3, 2014
    Inventors: Phillip Glen ELLISON, Jose Maria CARO, Michael James BARBARETTA, Robert Henry COWEN, Edward ANDERSEN, Necdet KURUL
  • Patent number: 8750449
    Abstract: The present invention allows to inhibit antiplane deformation of steel plates due to the back pressure generated by water content of the concrete, and allows observation of the concrete during a service period. In a steel concrete structure including an inner steel plate exposed to a high temperature environment, an outer steel plate, studs and concrete, a steam discharging pipe and a pipe opening are provided. The steam discharging pipe includes small openings. Water content inside the concrete evaporates in a state the temperature of the concrete reaches approximately 100° C., becomes steam, is concentrated in the vicinity of the rear surface of the steel plate, and is discharged to the outside of a containment vessel from the small openings through the steam discharging pipe.
    Type: Grant
    Filed: February 2, 2011
    Date of Patent: June 10, 2014
    Assignee: Hitachi-GE Nuclear Energy, Ltd.
    Inventors: Shintaro Narita, Masaaki Osaka
  • Patent number: 8731130
    Abstract: A power module assembly includes a reactor vessel containing a reactor core surrounded by a primary coolant. A containment vessel is adapted to be submerged in a containment cooling pool and to prohibit a release of the primary coolant outside of the containment vessel. A secondary cooling system is configured to remove heat generated by the reactor core. The heat is removed by circulating liquid from the containment cooling pool through the primary coolant.
    Type: Grant
    Filed: April 23, 2012
    Date of Patent: May 20, 2014
    Assignee: The State of Oregon Acting by and Through the State Board of Higher Education on Behalf of Oregon State University
    Inventors: Jose N. Reyes, Jr., John T. Groome
  • Patent number: 8681922
    Abstract: A thermal sleeve is mechanically attached to the bore of a surge nozzle of a pressurizer for the primary circuit of a pressurized water reactor steam generating system. The thermal sleeve is attached with a series of keys and slots which maintain the thermal sleeve centered in the nozzle while permitting thermal growth and restricting flow between the sleeve and the interior wall of the nozzle.
    Type: Grant
    Filed: December 14, 2010
    Date of Patent: March 25, 2014
    Assignee: Westinghouse Electric Company LLC
    Inventor: Robert M. Wepfer
  • Patent number: 8670517
    Abstract: A nuclear plant has a containment shell and a pressure relief pipe connected thereto in which a blowing device and a Venturi washer placed in a container with a washing liquid are connected in series. Even the finest particles or aerosols carried by air are held in the Venturi washer with a very high degree of reliability and the release thereof in environment is excluded in a particularly reliable manner in the case of decompression even associated with seal failures. For this purpose, the size of the blowing device and the Venturi washer are selected in such a way that during the operation of the blowing device a flow rate of liquid in the Venturi washer flowing to the decompressing pipe is higher than 130 m/sec, preferably higher than 180 m/sec.
    Type: Grant
    Filed: December 27, 2005
    Date of Patent: March 11, 2014
    Assignee: Areva GmbH
    Inventors: Bernd Eckardt, Robert Feuerbach
  • Publication number: 20140003568
    Abstract: A nuclear plant has a containment shell and a pressure relief pipe connected thereto in which a blowing device and a Venturi washer placed in a container with a washing liquid are connected in series. Even the finest particles or aerosols carried by air are held in the Venturi washer with a very high degree of reliability and the release thereof in environment is excluded in a particularly reliable manner in the case of decompression even associated with seal failures. For this purpose, the size of the blowing device and the Venturi washer are selected in such a way that during the operation of the blowing device a flow rate of liquid in the Venturi washer flowing to the decompressing pipe is higher than 130 m/sec, preferably higher than 180 m/sec.
    Type: Application
    Filed: December 27, 2005
    Publication date: January 2, 2014
    Inventors: Bernd Eckardt, Robert Feuerbach
  • Publication number: 20140003567
    Abstract: According to an embodiment, a nuclear power plant has a core; a reactor pressure vessel; a dry well; a wet well; a vacuum breaker; a containment vessel including the dry well, the LOCA vent pipe, the wet well, and the vacuum breaker; a cooling water pool placed outside the containment vessel; a heat exchanger at least partially submerged in cooling water; a gas supply pipe connected to the inlet plenum of the heat exchanger and the dry well; a condensate return pipe connected to the outlet plenum of the heat exchanger and the containment vessel; and a gas vent pipe connected to the outlet plenum of the heat exchanger and an outside of the wet well so that non-condensable gas inside the heat exchanger is released out of the wet well. The gas vent pipe is not connected to the wet well.
    Type: Application
    Filed: June 19, 2013
    Publication date: January 2, 2014
    Inventors: Takashi SATO, Keiji Matsumoto
  • Patent number: 8588360
    Abstract: A system includes a containment vessel configured to prohibit a release of a coolant, and a reactor vessel mounted inside the containment vessel. An outer surface of the reactor vessel is exposed to below atmospheric pressure, wherein substantially all gases are evacuated from within the containment vessel.
    Type: Grant
    Filed: March 4, 2009
    Date of Patent: November 19, 2013
    Assignee: The State of Oregon Acting by and Through the State Board of Higher Education on Behalf of Oregon State University
    Inventors: Jose N. Reyes, Jr., John T. Groome
  • Publication number: 20130301782
    Abstract: A nuclear reactor includes a nuclear reactor core disposed in a pressure vessel and immersed in primary coolant water at an operating pressure higher than atmospheric pressure. A containment structure contains the nuclear reactor. A reactor coolant inventory and purification system (RCI) is connected with the pressure vessel by make-up and letdown lines. The RCI includes a high pressure heat exchanger configured to operate responsive to a safety event at the operating pressure to remove heat from the primary coolant water in the pressure vessel. An auxiliary condenser located outside containment also removes heat. The RCI also includes a pump configured to inject make up water into the pressure vessel via the make-up line against the operating pressure. An emergency core cooling system (ECC) operates to depressurize the nuclear reactor only if the RCI and auxiliary condenser are unable to manage the safety event.
    Type: Application
    Filed: April 16, 2013
    Publication date: November 14, 2013
    Inventor: Babcock & Wilcox mPower, Inc.
  • Publication number: 20130287161
    Abstract: In one embodiment, the heat removal system includes a storage tank configured to store a heat transfer medium, a transfer system configured to selectively transfer the heat transfer medium from the storage tank to the nuclear reactor, and a delivery system operationally connected to the transfer system. The delivery system is configured to deliver the heat transfer medium to a suppression pool room of the nuclear reactor. The suppression pool room houses a suppression pool.
    Type: Application
    Filed: April 26, 2012
    Publication date: October 31, 2013
    Applicant: GE-HITACHI NUCLEAR ENERGY AMERICAS LLC
    Inventors: Eric P. Loewen, Charles L. Heck
  • Patent number: 8559583
    Abstract: A passive cooling and depressurization system for a pressurized water nuclear plant is provided with a cooling water pool, a steam supply piping, a heat exchanger, a steam supply valve, a coolant return pipe and an outlet valve. The steam supply piping extends from the gas phase of the pressurizer. The heat exchanger exchanges heat between water stored in the cooling water pool and steam flowing through the steam supply piping. The steam supply valve is equipped on the steam supply piping. The coolant return pipe extends from the heat exchanger to a liquid phase of the reactor pressure boundary. The outlet valve is equipped on the coolant return pipe.
    Type: Grant
    Filed: February 27, 2009
    Date of Patent: October 15, 2013
    Assignee: Kabushiki Kaisha Toshiba
    Inventors: Takashi Sato, Masanori Ino, Yasunobu Fujiki, Kazunori Hashimoto, Junichiro Otonari, Hisaki Sato, Naoko Matsunaga
  • Patent number: 8559584
    Abstract: A blocking device for preventing the actuation of an automatic depressurization system in a pressurized nuclear reactor system due to spurious signals resulting from a software failure. The blocking signal is removed when the coolant level within the core makeup tanks drop below a predetermined level.
    Type: Grant
    Filed: December 20, 2010
    Date of Patent: October 15, 2013
    Assignee: Westinghouse Electric Company LLC
    Inventor: Bruce M. Cook
  • Publication number: 20130259183
    Abstract: A passive cooling and depressurization system for a pressurized water nuclear plant is provided with a cooling water pool, a steam supply piping, a heat exchanger, a steam supply valve, a coolant return pipe and an outlet valve. The steam supply piping extends from the gas phase of the pressurizer. The heat exchanger exchanges heat between water stored in the cooling water pool and steam flowing through the steam supply piping. The steam supply valve is equipped on the steam supply piping. The coolant return pipe extends from the heat exchanger to a liquid phase of the reactor pressure boundary. The outlet valve is equipped on the coolant return pipe.
    Type: Application
    Filed: February 27, 2009
    Publication date: October 3, 2013
    Inventors: Takashi Sato, Masanori Ino, Yasunobu Fujiki, Kazunori Hashimoto, Junichiro Otonari, Hisaki Sato, Naoko Matsunaga
  • Patent number: 8528588
    Abstract: A safety valve drive system is operated such that a safety valve of a nuclear power plant is opened by supplying a driving gas by using a pilot valve at an occurrence of an accident or a transient state to thereby protect a reactor against pressure application. The safety valve drive system is provided with a safety valve drive unit, as a function of actuating the safety valve, and cables. The safety valve drive unit actuates in a manner that the safety valve is opened in response to respective auto-depressurization system actuating signals for two or more segments among respective auto-depressurization system actuating signals for four segments, and is closed if an auto-depressurization system actuating signal for one or less segment among the auto-depressurization system actuating signals for the four segments is received. The cables are connected to the safety valve drive unit and used to transfer the auto-depressurization system actuating signals for the four segments.
    Type: Grant
    Filed: June 17, 2008
    Date of Patent: September 10, 2013
    Assignee: Kabushiki Kaisha Toshiba
    Inventors: Hiroshi Yamazaki, Takeo Shimizu, Yuka Suzuki
  • Publication number: 20130182812
    Abstract: A method and a device depressurize a nuclear power plant. A depressurization flow is conducted out of a containment shell into the atmosphere via a depressurization line having a filter system. The filter system contains a filter chamber having an inlet, an outlet, and a sorbent filter. The depressurization flow is first conducted in a high-pressure section, then is depressurized by expansion at a throttle device, then conducted through the filter chamber having the sorbent filter, and finally blown out. To enable an effective retention of activity carriers contained in the depressurization flow, including organic compounds containing iodine, the depressurization flow depressurized by the throttle device is conducted through a superheating section before the depressurization flow enters the filter chamber, in which superheating section the depressurization flow is heated from the not yet depressurized depressurization flow to a temperature that is at least 10 ° C. above the dew point temperature.
    Type: Application
    Filed: February 25, 2013
    Publication date: July 18, 2013
    Applicant: AREVA NP GMBH
    Inventor: AREVA NP GMBH
  • Publication number: 20130129034
    Abstract: A hydrogen venting device for separating and releasing hydrogen gas from a gaseous mixture comprising hydrogen and steam generated in nuclear power plants is disclosed. The method includes providing a chamber at a high point in the cooling water circuit, allowing the collection chamber to cool below a gaseous mixture inlet temperature thereby allowing the hydrogen to collect at a first elevation within the collection chamber and condensate of the steam to collect at a second elevation within the collection chamber below the first elevation, and releasing substantially only hydrogen from the collection chamber at or proximal the first elevation when a threshold temperature, less than the first temperature, is reached.
    Type: Application
    Filed: November 21, 2011
    Publication date: May 23, 2013
    Applicant: VELAN INC.
    Inventors: A. Karel Velan, Vaclav Pauzer
  • Publication number: 20130094623
    Abstract: To install a safety/relief valve(S/RV) discharge line header in addition, on a current S/RV discharge lines in a BWR, can provide a steam release path to many quencher devices. Then the steam blowdown during the S/RV discharge can be more even or symmetrically distributed into the suppression pool in a BWR. The S/RV discharge line header is installed at the middle sections of either all or a portion of S/RV discharge pipes. A current S/RV discharge pipe is installed with a S/RV and a vacuum breaker and its discharge tailpipe is welded with the end of a quencher device inlet. The proposed discharge lines include components such as reactor safety/relief valves, discharge pipes, vacuum breakers, a discharge line header, quencher devices, etc.
    Type: Application
    Filed: December 19, 2011
    Publication date: April 18, 2013
    Applicant: Institute of Nuclear Energy Research Atomic Energy Council, Executive Yuan
    Inventors: JIN-SEN CHUNG, Shih-Jen Wang, Ying-Ruei Yuann
  • Publication number: 20130077730
    Abstract: A nuclear power plant has a reactor pressure vessel, a primary containment vessel and a passive pressure suppression pool cooling system. The reactor pressure vessel is installed in the primary containment vessel. A pressure suppression pool filled with cooling water is formed in a lower portion of the primary containment vessel. The passive pressure suppression pool cooling system is provided with a steam condensing pool in which cooling water is filled, disposed outside the primary containment vessel, a steam condenser disposed in the steam condensing pool, a steam supply pipe connecting the reactor pressure vessel to the steam condenser, and a condensed water discharge pipe connected to the steam condenser for discharging condensed water generated in the steam condenser. Another end portion of the condensed water discharge pipe is disposed in the pressure suppression pool.
    Type: Application
    Filed: July 19, 2012
    Publication date: March 28, 2013
    Applicant: Hitachi-GE Nuclear Energy, Ltd.
    Inventors: Kazuaki KITO, Masayoshi MATSUURA, Koji ANDO
  • Patent number: 8358732
    Abstract: Core debris generated during a molten reactor core in a reactor containment vessel penetrating the reactor containment vessel is configured to be caught by a core catcher located beneath the reactor containment vessel which has a main body having first stage cooling water channels and second stage surrounded by cooling fins extending radially. The number of the second stage cooling channels is larger than that of the first stage cooling channels. Cooling water is supplied from a cooling water injection opening and distributed to the first cooling water channels at a distributor. An intermediate header is formed between the first and the second cooling water channels, and the cooling water is distributed to the second cooling water channels uniformly.
    Type: Grant
    Filed: August 20, 2008
    Date of Patent: January 22, 2013
    Assignee: Kabushiki Kaisha Toshiba
    Inventors: Takashi Sato, Ryoichi Hamazaki, Mika Tahara, Yoshihiro Kojima, Hirohide Oikawa, Tomohisa Kurita, Seiichi Yokobori, Yuka Suzuki
  • Patent number: 8249212
    Abstract: A method for attaching a core spray sparger T-box clamp for a sparger T-box in a shroud of a nuclear reactor pressure vessel assembling the anchor plate, bearing plate and saddle bracket; positioning the assembly of the anchor plate, bearing plate and saddle bracket in front of the T-box such that the saddle bracket is below a sidewall of the T-box; elevating the assembly to seat the saddle bracket against a lower surface of the sidewall and sliding a locating pin on the saddle bracket into an aperture in the sidewall; lowering a carrier plate onto an upper surface of the sidewall and attaching the carrier plate to the anchor plate, wherein a locating pin on the carrier plate slides into an aperture on the upper surface, and advancing the bearing plate to the T-box to bias a bearing plate against a cover plate of the T-box.
    Type: Grant
    Filed: August 2, 2011
    Date of Patent: August 21, 2012
    Assignee: General Electric Company
    Inventors: Grant Clark Jensen, Robert W. Whitling
  • Patent number: 8218709
    Abstract: A nuclear installation has a reactor containment which is connected to a pressure relief line. A Venturi scrubber, which is arranged in a vessel containing a washing liquid, and a throttle device are connected in series in the pressure relief line. The novel system restrains, with particularly high reliability, fine air-transported activities or aerosols during decompression such that release thereof into the environment is practically impossible. The Venturi scrubber and the throttle device are dimensioned in such a way that, in the case of a critical drop in pressure of an air-vapor mixture flowing in the decompression line, a flow speed of said air-vapor mixture of more than 150 m/s, preferably more than 200 m/s, can be adjusted with respect to the throttle device in the Venturi scrubber.
    Type: Grant
    Filed: December 27, 2005
    Date of Patent: July 10, 2012
    Assignee: Areva NP GmbH
    Inventor: Bernd Eckardt
  • Publication number: 20120155597
    Abstract: A blocking device for preventing the actuation of an automatic depressurization system in a pressurized nuclear reactor system due to spurious signals resulting from a software failure. The blocking signal is removed when the coolant level within the core makeup tanks drop below a predetermined level.
    Type: Application
    Filed: December 20, 2010
    Publication date: June 21, 2012
    Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC
    Inventor: Bruce M. Cook
  • Publication number: 20120121057
    Abstract: A nuclear engineering plant has a containment, whose interior chamber is subdivided by a wall into a systems chamber and an operating chamber which is accessible during normal operation. The containment ensures a particularly high operational reliability, in particular also in incident situations, in which hydrogen is released in the systems chamber. For this purpose, a number of overflow openings are provided in the partition wall, the respective overflow opening is closed by a closure element of a closure apparatus which opens automatically when a trigger condition associated with the respective overflow opening is reached. Closure apparatuses are provided which open both as a function of pressure and independently of pressure. The closure apparatus furthermore has a closure element containing a bursting film or a bursting diaphragm. The closure apparatus is configured such that it frees the overflow opening automatically when a predetermined environment-side trigger temperature is reached.
    Type: Application
    Filed: January 12, 2012
    Publication date: May 17, 2012
    Applicant: AREVA NP GMBH
    Inventors: BERND ECKARDT, NORBERT LOSCH
  • Patent number: 8170173
    Abstract: A power module assembly includes a reactor vessel containing a reactor core surrounded by a primary coolant. A containment vessel is adapted to be submerged in a containment cooling pool and to prohibit a release of the primary coolant outside of the containment vessel. A secondary cooling system is configured to remove heat generated by the reactor core. The heat is removed by circulating liquid from the containment cooling pool through the primary coolant.
    Type: Grant
    Filed: May 15, 2008
    Date of Patent: May 1, 2012
    Assignee: The State of Oregon Acting by and Through the State Board of Higher Education on Behalf of Oregon State University
    Inventors: Jose N. Reyes, Jr., John T. Groome
  • Publication number: 20120076255
    Abstract: The present invention relates to an alternate feedwater injection system to at least partially mitigate the effects of an aircraft impact on a light water nuclear reactor positioned in a reactor building. The light water nuclear reactor has a primary system and a reactor core. The alternate feedwater injection system includes a water storage tank, an injection point into the primary system, a pump capable to transfer water from the water storage tank to the injection point and ultimately to the reactor core. The water storage tank and pump are located external to a reactor building and outside of an identified aircraft impact area or inside the identified aircraft impact area and provided with a means of protection from the aircraft impact.
    Type: Application
    Filed: September 24, 2010
    Publication date: March 29, 2012
    Applicant: Westinghouse Electric Company LLC
    Inventors: Nirmal Jain, James R. Nowell, Subhash Chandra, Edward E. Berry
  • Publication number: 20120051488
    Abstract: A method and a corresponding device for the pressure relief of a nuclear power plant having an outlet for a relief flow. The relief flow is guided out of a containment into the atmosphere via a relief line provided with a filter system. The filter system has a filter chamber with a filter-chamber inlet and outlet and a sorbent filter arranged therebetween. The relief flow is guided in a high-pressure section of the relief line past the filter chamber, with the latter being heated, and the relief flow is expanded at the end of the high-pressure section and dried. In order for efficient retention of iodine-containing organic compounds, the relief flow is guided through a bed filter, guided in a superheating section past the high-pressure section of the relief line and in the process is heated, guided in this state directly thereafter through the filter chamber having the sorbent filter.
    Type: Application
    Filed: August 25, 2011
    Publication date: March 1, 2012
    Applicant: AREVA NP GMBH
    Inventors: BERND ECKARDT, NORBERT LOSCH, CARSTEN PASLER