By Particular Instrumentation Circuitry Patents (Class 376/259)
  • Patent number: 9983575
    Abstract: Systems and methods to graphically display process control system information are disclosed. Some example methods include monitoring process variables in a process control system, determining a current state of a first one of the process variables, and determining a trend associated with the first process variable. Some such examples further include generating a first graphic representative of information associated with the first process variable, the information comprising the current state of the first process variable and the trend of the first process variable. Some example methods also include rendering the first graphic via a display.
    Type: Grant
    Filed: April 9, 2013
    Date of Patent: May 29, 2018
    Assignee: FISHER-ROSEMOUNT SYSTEMS, INC.
    Inventors: Mark Nixon, Maia B. Cook, Daniel I. Manes, Harvey S. Smallman
  • Patent number: 9733368
    Abstract: According to an embodiment, a neutron measurement apparatus has: a neutron detector; a preamplifier that amplifies an output signal of the neutron detector and outputs a neutron detection signal; a pulse counting unit that measures the neutron intensity by using pulse counting method by which the neutron detection signal is used to count the number of individual pulses; a Campbell measurement unit that measures the neutron intensity by using Campbell method by which a time average of squares of AC component of the neutron detection signal is calculated; a correction constant calculation unit that calculates a correction constant for correcting an output of the Campbell measurement unit by using an output of the pulse counting unit and an output of the Campbell measurement unit; and a correction value calculation unit that outputs, based on the output of the Campbell measurement unit, a corrected value by using the correction constant.
    Type: Grant
    Filed: October 29, 2015
    Date of Patent: August 15, 2017
    Assignee: Kabushiki Kaisha Toshiba
    Inventors: Shigehiro Kono, Daijiro Ito, Makoto Tomitaka, Tsuyoshi Kumagai, Norihiro Umemura
  • Patent number: 9685246
    Abstract: A control system allows controlling a nuclear facility in an evacuation area. The control system includes a control device in ordinary use disposed in a non-evacuation area, an emergency control device—for emergency in the evacuation area, a plant control facility connectable to the control device—and the emergency control device, a signal switching unit that switches from a normal coupling to an emergency coupling based on an emergency switch signal, a first selector switch in the non-evacuation area, a second selector switch-in the evacuation area, an AND circuit configured to output the emergency switch signal to the signal switching unit in the case where the emergency switch signal is input from the first selector switch and the emergency switch signal is input from the second selector switch.
    Type: Grant
    Filed: September 13, 2011
    Date of Patent: June 20, 2017
    Assignee: MITSUBISHI HEAVY INDUSTRIES, LTD.
    Inventors: Hiroshi Fujimoto, Hironobu Shinohara, Yasutake Akizuki, Toshiki Fukui, Yuichi Tanaka, Shinji Kiuchi, Hiroshi Shirasawa
  • Patent number: 9558856
    Abstract: In a control system for a plant controlling a plant such as a nuclear power plant 1 with use of a plurality of digital control devices 41, the plurality of digital control devices 41 include a plurality of control functions 46 to 56, and the plurality of control functions 46 to 56 are provided in the plurality of digital control devices 41 in a distributed manner so that the digital control devices 41 may not fall below safety standards preset by safety analyses. This provides a control system for a plant using the plurality of digital control devices 41 and configured to control a plant safely even when a digital control device is failed.
    Type: Grant
    Filed: August 2, 2011
    Date of Patent: January 31, 2017
    Assignee: MITSUBISHI HEAVY INDUSTRIES, LTD.
    Inventors: Tetsuro Nagai, Hidekazu Satake
  • Patent number: 9368240
    Abstract: Provided are a safety protection system facility 43 outputting a normal actuating signal S1 in a case where the safety protection system facility 43 controls actuation of a unit provided in a nuclear facility to a safe side based on an abnormality detecting signal output at the time of occurrence of an abnormality in the nuclear facility, and where this causes the unit to be actuated normally, and a CCF countermeasure facility 44 outputting a CCF-case actuating signal S2 actuating the unit to a safe side in a case where the CCF countermeasure facility 44 determines from output results of the abnormality detecting signal and the normal actuating signal S1 that the unit is not actuated normally at the time of occurrence of the abnormality in the nuclear facility.
    Type: Grant
    Filed: August 2, 2011
    Date of Patent: June 14, 2016
    Assignee: MITSUBISHI HEAVY INDUSTRIES, LTD.
    Inventors: Masafumi Utsumi, Hidekazu Satake, Masaru Shimizu
  • Patent number: 9355477
    Abstract: A method includes partitioning alarms into two or more alarm groups. The alarms are associated with operation of an industrial process system performing a process, and each alarm has multiple states. The method also includes generating a graphical display for presentation to a user. The graphical display identifies at least one of the alarm groups and multiple alarm indicators. Each alarm indicator indicates a state transition of an associated alarm between two of the alarm's states. The alarm indicators are arranged in the graphical display based on times of their respective state transitions.
    Type: Grant
    Filed: June 28, 2011
    Date of Patent: May 31, 2016
    Assignee: Honeywell International Inc.
    Inventors: Craig Stuart Ashley, David Barry Granatelli, Joseph Cho Hei Cheung, Donald Maxwell Shepherd, Robert Andrew Weiss, Benjamin Ivan Schultz
  • Patent number: 9335380
    Abstract: The invention is related to a device for detecting insulation degradation in an inverter-driven load device, in particular a motor, the device including: zero-phase current measuring means for measuring a zero-phase current in power-feed lines, provided in the power-feed lines between an inverter device and the motor; and command control means for putting rotation of the motor on standby; wherein the zero-phase current measuring means measures the total of phase currents fed into respective phases so as not to rotate a shaft even when an external force is applied to the shaft during the rotation being on standby, whereby allowing regular detection of insulation degradation without switching over the power-feed lines connected with the load device.
    Type: Grant
    Filed: February 8, 2010
    Date of Patent: May 10, 2016
    Assignee: Mitsubishi Electric Corporation
    Inventors: Yoshimasa Watanabe, Ryuichi Nishiura, Yoshiharu Kaneda, Hiroshi Nishizawa, Toru Oka, Hirotaka Muto, Toshiki Tanaka, Yoji Tsutsumishita
  • Patent number: 9275764
    Abstract: In an operation monitoring apparatus of a nuclear power plant, a first operation console (12) that can be operated by an operator and includes displays (31 to 37), an operation command console (14) that can be operated by a shift supervisor and includes displays (41 to 44) , a transfer device (51) that can display an image displayed on the displays (31 to 37) of the first operation console (12) on the displays (41 to 44) of the operation command console (14), and a switching device (54) that switches an image on the displays (41 to 44) of the operation command console (14) to the image on the displays (31 to 37) of the first operation console transferred by the transfer device (51) are provided. With this configuration, it is possible to improve communications between the supervisor and the operation in operation of the nuclear power plant.
    Type: Grant
    Filed: July 25, 2011
    Date of Patent: March 1, 2016
    Assignee: MITSUBISHI HEAVY INDUSTRIES, LTD.
    Inventors: Satoshi Hanada, Koji Ito
  • Patent number: 9253219
    Abstract: A system and method to influence routing of a call by a sequenced application from among a plurality of sequenced applications is disclosed. The method comprises receiving a header for the call wherein the header comprises at least one directive from each of the plurality of sequenced applications. Further the method comprises arbitrating conflicts from among the one directive in the header in order to determine a set of sequenced application headers to at least partially execute. Finally, the determined set of sequenced application headers is at least partially executed.
    Type: Grant
    Filed: March 30, 2012
    Date of Patent: February 2, 2016
    Assignee: Avaya Inc.
    Inventors: Timothy I. Ross, Harsh V. Mendiratta, Rajeshwari Edamadaka
  • Patent number: 9202599
    Abstract: Provided are an operation support device and an operation support method for a nuclear power plant which are capable of accurately grasping the condition of a nuclear power plant and capable of offering support for instantly performing a predetermined operation by an operator when an unusual situation occurs. The operation support device for a nuclear power plant is provided with an operation state check display unit (20) for displaying whether or not a system or equipment necessary for a safe operation of the entire nuclear power plant operates on the basis of a command signal to the system or equipment and a bypass and operation impossibility state display unit (21) for displaying whether the system or equipment is operable or not.
    Type: Grant
    Filed: October 25, 2010
    Date of Patent: December 1, 2015
    Assignee: MITSUBISHI HEAVY INDUSTRIES, LTD.
    Inventors: Masanori Yokoyama, Koji Ito
  • Patent number: 9177676
    Abstract: Provide a nuclear reactor power monitoring technology for enhancing the monitoring accuracy and reliability in nuclear thermal hydraulic stability.
    Type: Grant
    Filed: May 11, 2011
    Date of Patent: November 3, 2015
    Assignee: KABUSHIKI KAISHA TOSHIBA
    Inventors: Yutaka Takeuchi, Hiroshi Ono, Kazuki Yano
  • Patent number: 8964926
    Abstract: An ex-core nuclear instrumentation system in which the width of measurable neutron detector current can be accurately widened is obtained. In order to output the condition of neutron flux in operation by performing arithmetic processing of a current value measured by a neutron detector by using a detector signal processing circuit, the detector signal processing circuit includes a current/voltage conversion unit which converts the current value converted by the neutron detector into a voltage value corresponding to the current value; and a variable gain amplification unit which has an operational amplifier having a resistance circuit for corresponding to current levels, the resistance circuit being capable of selecting a gain, and a D/A converter that adjusts the gain, and amplifies the voltage value converted by the current/voltage conversion unit.
    Type: Grant
    Filed: September 15, 2011
    Date of Patent: February 24, 2015
    Assignee: Mitsubishi Electric Corporation
    Inventors: Shingo Nakamura, Tatsuro Kobayashi
  • Publication number: 20140369456
    Abstract: Systems and methods of monitoring rod control systems of nuclear power plants, including: measuring a particular signal applied to at least one coil of a rod movement mechanism at one or more predetermined times relative to an initial energizing of a mechanism coil; comparing the measured signal to a reference signal parameter, and determining if the measured signal deviates from the reference signal parameter by a predetermined amount to indicate degradation of the rod control system.
    Type: Application
    Filed: June 18, 2013
    Publication date: December 18, 2014
    Inventors: Samuel D. Caylor, Jacob R. McCulley, Gregory W. Morton, Hashem M. Hashemian
  • Publication number: 20140355730
    Abstract: According to one embodiment, a reactor oscillation power range monitor includes: a receiving unit configured to receive LPRM signals issued by LPRM detectors differing in vertical position out of a plurality of LPRM detectors placed in a reactor core; a specification unit configured to specify any exclusion signal which meets an exclusion condition out of the received LPRM signals; an estimation unit configured to estimate an alternative signal for the exclusion signal based on a regular signal which does not meet the exclusion condition out of the received LPRM signals; an arithmetic averaging unit configured to output an arithmetically averaged signal obtained by arithmetically averaging the regular signal and the alternative signal; a time averaging unit configured to output a time-averaged signal obtained by time-averaging the arithmetically averaged signal; and a calculation unit configured to output a standard value obtained by dividing the arithmetically averaged signal by the time-averaged signal.
    Type: Application
    Filed: May 29, 2014
    Publication date: December 4, 2014
    Applicant: KABUSHIKI KAISHA TOSHIBA
    Inventors: SEIGO SATO, TADASHI MIYAZAKI, TOSHIAKI ITO, NAOTAKA ODA, YASUSHI GOTO, YUTAKA TAKEUCHI, KAZUKI YANO, NORIO SAKAI
  • Patent number: 8885789
    Abstract: A device for measuring and correcting a parallelism error of an upper plug end of a nuclear fuel rod comprising mechanisms for measuring a parallelism error and for correcting said error, and a mechanism for positioning said device on the fuel rod and cooperating with a rack on which the fuel rod is stored, said correction means being arranged opposite the measuring mechanism relative to the location of the fuel rod, in order to allow a measurement of the parallelism error during correction of said error.
    Type: Grant
    Filed: September 14, 2009
    Date of Patent: November 11, 2014
    Assignee: Areva NC
    Inventor: Daniel Lavios
  • Publication number: 20140307843
    Abstract: A reactor in-core instrument handling system in which the signal leads are routed from the instrument sensors through an outer sheath through the upper reactor internals and out of and around the sheath in a substantially tightly wound spiral before exiting the reactor vessel.
    Type: Application
    Filed: April 11, 2013
    Publication date: October 16, 2014
    Applicant: Westinghouse Electric Company LLC
    Inventor: Kenneth V. Margotta
  • Publication number: 20140270041
    Abstract: Various embodiments enable wireless monitoring of a radioactive environment and related operating conditions. Structures of increasing complexity and formed at least in part from a semiconductor material based on crystalline actinide oxide-based material enable monitoring at least one operating conditions of the radioactive environment. An exemplary embodiment is a device comprising one or more crystal oscillator units that can generate a first oscillating signal, and an actinide oxide-based unit functionally coupled to at least one of the one or more crystal oscillator units, and configured to receive the first oscillating signal. The actinide oxide-based unit can supply a second oscillating signal to an antenna that delivers the second oscillating signal wirelessly, wherein the second oscillating signal is based on the first oscillating signal and is indicative of an operating condition of the radioactive environment. The antenna is part of the radioactive environment.
    Type: Application
    Filed: March 13, 2013
    Publication date: September 18, 2014
    Applicant: Idaho State University
    Inventor: Idaho State University
  • Patent number: 8831162
    Abstract: A reactor core coolant temperature measuring apparatus for measuring the temperature of the coolant flowing in the reactor core of a nuclear reactor comprises a ?-ray thermometer having a temperature measuring section arranged below the bottom of the reactor core and a ?-ray heat generation detecting section arranged between the bottom and the top of the reactor core, a cable for transmitting the signal output from the temperature measuring section and an output signal processing means for receiving the signal and computationally determining the local temperature of the coolant at the position of placement of the temperature measuring section.
    Type: Grant
    Filed: September 14, 2006
    Date of Patent: September 9, 2014
    Assignee: Kabushiki Kaisha Toshiba
    Inventors: Naotaka Oda, Tadashi Miyazaki
  • Patent number: 8824617
    Abstract: Systems and methods of monitoring position information of a control rod in a nuclear reactor, including detecting an output signal induced by movement of a control rod with respect to at least one detection coil of the control rod, the output signal having identifiable characteristics representative of a plurality of positions of the control rod within the at least one detection coil, and processing the identifiable characteristics to derive the positions of the control rod within the at least one detection coil.
    Type: Grant
    Filed: December 7, 2012
    Date of Patent: September 2, 2014
    Assignee: Analysis and Measurement Services Corporation
    Inventors: Casey D. Sexton, Danny D. Beverly, Gregory W. Morton, Hashem M. Hashemian, Brent D. Shumaker
  • Patent number: 8781058
    Abstract: A device for detecting steel is provided. The steel is used in a nuclear plant. The device has a detecting circuit of electrochemical corrosion potential (ECP) and alternative current (AC) impedance. An environment in a boiling water reactor (BWR) is simulated under hydrogen water chemistry (HWC). The environment is used for detecting intergranular stress corrosion cracking (IGSCC) of components coated with different precious metals. Thus, effect of coating different precious metals on steels can be evaluated for HWC.
    Type: Grant
    Filed: October 1, 2010
    Date of Patent: July 15, 2014
    Assignee: Institute of Nuclear Energy Research, Atomic Energy Council
    Inventors: Tung-Jen Wen, Ning-Yih Hsu
  • Patent number: 8774340
    Abstract: A nuclear reactor vibration surveillance system has a first ultrasonic transducer for transmission, an ultrasonic transmitter, a second ultrasonic transducer for reception, an ultrasonic receiver, a signal processor, and a display unit. The first ultrasonic transducer for transmission is arranged on the outer surface of a reactor pressure vessel and is configured to convert a transmission signal into an ultrasonic pulse signal and allow the ultrasonic pulse to be transmitted to a reactor internal component. The second ultrasonic transducer for reception is arranged on the outer surface of the reactor pressure vessel and is configured to receive a reflected ultrasonic pulse reflected by the reactor internal component and convert the received reflected ultrasonic pulse into a reception signal.
    Type: Grant
    Filed: March 23, 2009
    Date of Patent: July 8, 2014
    Assignee: Kabushiki Kaisha Toshiba
    Inventors: Hidehiko Kuroda, Mikio Izumi, Mitsuhiro Enomoto, Masaki Yoda, Mieko Sato
  • Patent number: 8744033
    Abstract: An object of the invention is to embody a small and inexpensive passage selector, which can be applied by commonly using an index device even if the number of detector passages is changed, and which is easy to make inspection and maintenance. The passage selector of a reactor in-core nuclear-measuring apparatus of the invention includes: a drive motor; an index device that is driven by the drive motor and that makes a rotary output of a predetermined index number; a central rotating shaft that is driven to rotate by the index device and that causes a passage selecting guide tube to be located in opposition to any detector passage; and a speed-increasing and decreasing device that is interposed between an output shaft of the index device and the central rotating shaft, and that adjusts the index number of the central rotating shaft.
    Type: Grant
    Filed: November 14, 2008
    Date of Patent: June 3, 2014
    Assignee: Mitsubishi Electronic Corporation
    Inventors: Kenji Oosaka, Masami Yodogawa
  • Publication number: 20140140464
    Abstract: A system for monitoring a condition of a nuclear reactor pressure vessel disposed in a radioactive environment includes an instrument structured to monitor a condition of the nuclear reactor pressure vessel; a powered wireless transmitting modem disposed in the radioactive environment, the wireless transmitting modem being electrically coupled to the instrument; a receiving modem disposed in the line of sight of the transmitting modem, the receiving modem being in wireless communication with the transmitting modem; and a signal processing unit electrically coupled to the receiving modem, the signal processing unit being structured to determine the condition of the nuclear reactor pressure vessel from the instrument. The transmitting modem is powered by a thermocouple disposed in or on the reactor pressure vessel.
    Type: Application
    Filed: October 18, 2013
    Publication date: May 22, 2014
    Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC
    Inventor: RICHARD W. MORRIS
  • Patent number: 8699654
    Abstract: The invention concerns a method comprising measurement on a fuel channel (14) of fuel assemblies (8) for nuclear boiling water reactors. The method comprises that: the measurement is done by the use of a non-destructive inductive eddy current measurement method, the measurement is done on a fuel channel (14) which has been used at least a certain time during operation in the core of a nuclear boiling water reactor, the measurement is done when the fuel channel (14) is located in water, the measurement is done on different places on the fuel channel (14), wherein through the method at least the hydride content of the fuel channel (14) at said places is determined. The method can be used in order to find out how shadow corrosion from a neighboring control rod influences the properties of the fuel channel (14).
    Type: Grant
    Filed: June 8, 2009
    Date of Patent: April 15, 2014
    Assignee: Westinghouse Electric Sweden AB
    Inventors: Kurt-Åke Magnusson, Holger Wiese, Björn Andersson, Göran Jergeus
  • Publication number: 20140098923
    Abstract: The invention relates to an apparatus and methods for operation in relatively high radiation fields to remotely switch signal devices through a shared single main umbilical signal cable. The invention is particularly suitable for use in a nuclear reactor, such as a boiling water reactor, and in difficult to access areas in the reactor pressure vessel. One or more main umbilical cables connect a control station to an enclosure housing a signal switching device. The signal switching device allows several signal generating/receiving devices, such as cameras and ultrasonic probes, to be controlled by the one or more main umbilical cables.
    Type: Application
    Filed: March 15, 2013
    Publication date: April 10, 2014
    Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC
    Inventor: WESTINGHOUSE ELECTRIC COMPANY LLC
  • Patent number: 8675805
    Abstract: Provided is an automated periodic surveillance testing method and apparatus in a digital reactor protection system, which unites a passive testing means such as a self-diagnosis or an on-line state comparison with an active testing means such as an automatic logic test and the like in the digital reactor protection system. Accordingly, a device self-diagnosis, an on-line state diagnosis, and an automatic logic test are used as the automated periodic surveillance testing method in the digital reactor protection system. Thus, the time consumed in a periodic surveillance test can be minimized, thereby saving reactor operating costs, and excessive manpower can be avoided, thereby decreasing potential human errors. Also, a channel detour time at which one of multiple channels is detoured can be minimized based on the automated periodic surveillance test in the digital reactor protection system, thereby enhancing stability.
    Type: Grant
    Filed: December 7, 2010
    Date of Patent: March 18, 2014
    Assignees: Korea Atomic Energy Research Institute, Korea Hydro & Nuclear Power Co., Ltd.
    Inventors: Seop Hur, Inkoo Hwang, Dong-Hoon Kim, Jung Taek Kim, Jong-Gyun Choi, Jung-Woon Lee, Gee Yong Park, Jae-Chang Park, Dong-Young Lee, Kee-Choon Kwon
  • Patent number: 8605851
    Abstract: To provide a rod block monitor in which irrespective of the selection or non-selection of a control rod, such a process is repeatedly executed that gain adjustment is performed at fixed intervals at all times to match a local area average value of signals of neutron detectors surrounding the control rod with a nuclear reactor average power and a block level appropriate to the local area average value of the neutron detector signals after the gain adjustment is set.
    Type: Grant
    Filed: July 28, 2006
    Date of Patent: December 10, 2013
    Assignee: Kabushiki Kaisha Toshiba
    Inventors: Naotaka Oda, Yasushi Goto, Tadashi Miyazaki
  • Patent number: 8555917
    Abstract: A motor operated valve diagnostic data acquisition system including: a motor operated valve assembly; a transmitter, the transmitter being permanently connected in a housing of a motor operated valve assembly; a receiver, the transmitter transmitting signals to the receiver via motor operated valve cables, the cables being existing motor operated valve cables; and electronic circuitry connected to the receiver, the electronic circuitry processing the signals received by the receiver.
    Type: Grant
    Filed: March 16, 2010
    Date of Patent: October 15, 2013
    Assignee: Areva NP Inc
    Inventors: Vedat T. Ataman, Lew McKeague
  • Publication number: 20130182811
    Abstract: An ultrasonic sensor has a piezo-electric element attached at an end surface outside a reactor pressure vessel (RPV) of a sensor leading edge portion. The sensor leading edge portion passes through a bottom head of the RPV and is installed on the bottom head. Ultrasonic waves generated by the piezo-electric element are propagated to the sensor leading edge portion and are propagated to reactor water in the RPV from the sensor leading edge portion. When water surface of the reactor water in the RPV exists below a core support plate, the ultrasonic waves propagated inside the reactor water are reflected on the water surface. Ultrasonic waves reflected on the water surface are propagated into the reactor water, enter the sensor leading edge portion, and are received by the piezo-electric element. Using the ultrasonic waves received by the piezo-electric element, the water level in the RPV is obtained.
    Type: Application
    Filed: December 28, 2012
    Publication date: July 18, 2013
    Applicant: HITACHI-GE NUCLEAR ENERGY, LTD.
    Inventor: HITACHI-GE NUCLEAR ENERGY, LTD.
  • Patent number: 8477899
    Abstract: A method of operating a nuclear reactor is disclosed. The reactor (1) encloses a core having a plurality of fuel rods (9). Each fuel rod (9) includes a cladding and fuel pellets of a nuclear fuel. The fuel pellets are arranged in an inner space of the cladding leaving a free volume comprising an upper plenum, a lower plenum and a pellet-cladding gap. The reactor is operated at a normal power and a normal inlet sub-cooling during a normal state. The reactor is monitored for detecting a defect on the cladding of any of the fuel rods. The operation of the reactor is changed to a particular state after detecting such a defect. The particular state permits an increase of the free volume in the defect fuel rod. The reactor is operated at the particular state during a limited time period, after which the reactor is operated at the normal state.
    Type: Grant
    Filed: April 7, 2008
    Date of Patent: July 2, 2013
    Assignee: Westinghouse Electric Sweden AB
    Inventors: Sture Lennart Helmersson, Nils Magnus Limback, Jonathan Michael Wright
  • Publication number: 20130142298
    Abstract: An in-core nuclear instrumentation apparatus is provided with a neutron flux current detection circuit which converts a neutron flux current signal fed from a neutron detector into a voltage signal and amplifies the voltage signal with a capability to continuously vary amplifier gain. The neutron flux current detection circuit includes a current sensing resistor for converting the neutron flux current signal into the voltage signal, an amplifier for amplifying the voltage signal, wherein an equivalent resistance value of a feedback circuit of the amplifier can be controllably varied, an equivalent resistance control circuit for varying the equivalent resistance value of the feedback circuit, and an output circuit which outputs an output terminal voltage signal of the amplifier.
    Type: Application
    Filed: April 16, 2012
    Publication date: June 6, 2013
    Applicant: Mitsubishi Electric Corporation
    Inventors: Toshihiko NAKANOSONO, Masaru Tamuro
  • Patent number: 8451100
    Abstract: Described is the use of a transponder in a commercial installation, particularly a power plant, which allows problems and dangerous situations existing in this context to be avoided and the attainable occupational safety in a commercial installation, particularly a power plant, to be increased. The transponder includes a reception element, a transmission element, a visual display unit and a memory element and also a control element which is operatively connected to these, in a commercial installation, particularly a power plant, in an arrangement or positioning on or in proximity to a component or at a switching or measuring point associated with the component for the purpose of visually displaying an operating state for the component or the switching or measuring point associated therewith using the visual display unit of the transponder.
    Type: Grant
    Filed: October 13, 2009
    Date of Patent: May 28, 2013
    Assignee: STEAG Energy Services GmbH
    Inventors: Wolfgang Offermann, Martin Stephan
  • Publication number: 20130129030
    Abstract: In an operation monitoring apparatus of a nuclear power plant, a first operation console (12) that can be operated by an operator and includes displays (31 to 37), an operation command console (14) that can be operated by a shift supervisor and includes displays (41 to 44) , a transfer device (51) that can display an image displayed on the displays (31 to 37) of the first operation console (12) on the displays (41 to 44) of the operation command console (14), and a switching device (54) that switches an image on the displays (41 to 44) of the operation command console (14) to the image on the displays (31 to 37) of the first operation console transferred by the transfer device (51) are provided. With this configuration, it is possible to improve communications between the supervisor and the operation in operation of the nuclear power plant.
    Type: Application
    Filed: July 25, 2011
    Publication date: May 23, 2013
    Applicant: MITSUBISHI HEAVY INDUSTRIES, LTD.
    Inventors: Satoshi Hanada, Koji Ito
  • Patent number: 8442181
    Abstract: An apparatus for inspecting and testing a startup range neutron monitoring system for a nuclear reactor. The apparatus includes: a neutron-flux detector; a preamplifier that amplifies an electric signal output from the neutron-flux detector; a pulse measurement unit that counts times when electric signal output from the preamplifier exceeds a discrimination voltage; a discrimination-voltage setting unit that applies the discrimination voltage to the pulse measurement unit; a voltage-setting unit that applies a voltage to the neutron-flux detector; an arithmetic processing unit that calculates an output power of the reactor based upon an output signal of the pulse measurement unit; an output unit that outputs data representing the output power of the reactor, calculated by the arithmetic processing unit; and an inspecting/testing unit that sets the discrimination voltage and the voltage to be applied by the voltage-setting unit.
    Type: Grant
    Filed: January 24, 2012
    Date of Patent: May 14, 2013
    Assignee: Kabushiki Kaisha Toshiba
    Inventor: Hideyuki Kitazono
  • Patent number: 8433029
    Abstract: In one embodiment, the method includes determining the safety limit minimum critical power ratio using the operating limit minimum critical power ratio, a change-in-critical-power-ratio distribution bias and a change-in-critical-power-ratio distribution standard deviation.
    Type: Grant
    Filed: December 14, 2007
    Date of Patent: April 30, 2013
    Assignee: Global Nuclear Fuel—Americas, LLC
    Inventor: James Edward Fawks, Jr.
  • Patent number: 8406368
    Abstract: An upper detector and a lower detector that face at least one side of a fuel assembly, on which neutrons are irradiated in a nuclear reactor, and detect radiation are set at a predetermined interval in an axial direction of the fuel assembly. Distributions of radiation signals are measured by the upper detector and the lower detector while the fuel assembly and the upper detector and the lower detectors are relatively moved along the axial direction of the fuel assembly. Soundness of radiation signals measured by the upper detector and the lower detector is determined in every measurement by comparing radiation signal distributions obtained by measuring the same portion in the axial direction of the fuel assembly in a multiplexed manner with the upper detector and the lower detector. Thereafter, relative burn-up is calculated by utilizing the measured radiation signals to measure a burn-up profile.
    Type: Grant
    Filed: April 11, 2008
    Date of Patent: March 26, 2013
    Assignee: Kabushiki Kaisha Toshiba
    Inventors: Hironori Kumanomido, Naotaka Oda, Yutaka Tokiwa, Makoto Ueda
  • Patent number: 8380477
    Abstract: The present invention certifies control modules of engineered safety feature instruments for a power plant automatically. The control modules can be tested before storing or operating. The test is done with enhanced testing speed and saved cost. Thus, safety of the control modules is confirmed.
    Type: Grant
    Filed: January 8, 2010
    Date of Patent: February 19, 2013
    Assignee: Atomic Energy Council—Institute of Nuclear Energy Research
    Inventors: Ben-Ching Liao, Yuan-Chang Yu, Huei-Wen Hwang, Tsung-Chieh Cheng, Minh-Huei Chen
  • Patent number: 8351561
    Abstract: An advanced digital rod position indication (ADRPI) system having rod drop monitoring capability. When a reactor trip occurs, the ADRPI system derives the rod drop time from the signals induced in the detector coils by the falling drive rods. The ADRPI system is linked to the reactor trip breaker to provide a reference point to allow accurate timing of the rod drop times.
    Type: Grant
    Filed: January 9, 2009
    Date of Patent: January 8, 2013
    Assignee: Analysis and Measurement Services Corporation
    Inventors: Hashem M. Hashemian, Gregory W. Morton, Brent D. Shumaker, Danny D. Beverly, Casey D. Sexton
  • Patent number: 8331521
    Abstract: According to an embodiment, a digital process type monitor device includes a plurality of modules and a mother board connected to each of the modules. Each module includes: a base board connected to a connector and having an FPGA for main control and an IPGA for sub board control mounted thereon; and a sub board for a main-machine I/F process, having an FPGA for an I/F process mounted hereon. Each sub board has storage devices for storing man-machine I/F information on the sub board. Each of the FPGA writes transmission data into a predetermined region of a transmission area and has a common transmission protocol to share the transmission data between the respective modules.
    Type: Grant
    Filed: December 1, 2010
    Date of Patent: December 11, 2012
    Assignee: Kabushiki Kaisha
    Inventors: Masataka Yanagisawa, Toshifumi Sato
  • Patent number: 8290111
    Abstract: The invention provides at least two electrochemical sensors positioned in a nuclear reactor or in a system adjacent to the nuclear reactor, wherein at least one of the at least two electrochemical sensors has a heated zirconium electrode, and the at least two electrochemical sensors produce voltages proportional to an electrochemical corrosion potential for a surface that each of the at least two electrochemical sensors are installed upon. The invention also provides an arrangement configured to accept the voltages produced by the at least two electrochemical sensors, wherein the arrangement is configured to determine an electrochemical corrosion potential of a zirconium fuel rod in the nuclear reactor based upon the voltages of the at least two electrochemical sensors.
    Type: Grant
    Filed: May 25, 2007
    Date of Patent: October 16, 2012
    Assignees: Areva NP Inc., Areva NP GmbH
    Inventors: Mihai G. M. Pop, Brian G. Lockamon, Hans-Jürgen Sell, Renate Kilian
  • Publication number: 20120177166
    Abstract: An in-core neutron monitor that employs vacuum microelectronic devices to configure an in-core instrument thimble assembly that monitors and wirelessly transmits a number of reactor parameters directly from the core of a nuclear reactor without the use of external cabling. The in-core instrument thimble assembly is substantially wholly contained within an instrument guide tube within a nuclear fuel assembly.
    Type: Application
    Filed: January 7, 2011
    Publication date: July 12, 2012
    Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC
    Inventors: John G. Seidel, Robert W. Flammang, Jorge V. Carvajal, Michael A. James, Nicola G. Arlia
  • Patent number: 8194814
    Abstract: A neutron detector system for discriminating fissile material from non-fissile material wherein a digital data acquisition unit collects data at high rate, and in real-time processes large volumes of data directly into information that a first responder can use to discriminate materials. The system comprises counting neutrons from the unknown source and detecting excess grouped neutrons to identify fission in the unknown source. The system includes a graphing component that displays the plot of the neutron distribution from the unknown source over a Poisson distribution and a plot of neutrons due to background or environmental sources. The system further includes a known neutron source placed in proximity to the unknown source to actively interrogate the unknown source in order to accentuate differences in neutron emission from the unknown source from Poisson distributions and/or environmental sources.
    Type: Grant
    Filed: October 26, 2007
    Date of Patent: June 5, 2012
    Assignee: Lawrence Livermore National Security, LLC
    Inventors: Mark S. Rowland, Neal J. Snyderman
  • Publication number: 20120121055
    Abstract: Provided are an operation support device and an operation support method for a nuclear power plant which are capable of accurately grasping the condition of a nuclear power plant and capable of offering support for instantly performing a predetermined operation by an operator when an unusual situation occurs. The operation support device for a nuclear power plant is provided with an operation state check display unit (20) for displaying whether or not a system or equipment necessary for a safe operation of the entire nuclear power plant operates on the basis of a command signal to the system or equipment and a bypass and operation impossibility state display unit (21) for displaying whether the system or equipment is operable or not.
    Type: Application
    Filed: October 25, 2010
    Publication date: May 17, 2012
    Applicant: MITSUBISHI HEAVY INDUSTRIES, LTD.
    Inventors: Masanori Yokoyama, Koji Ito
  • Publication number: 20120114089
    Abstract: Disclosed herein are apparatus and methods for detecting and quantifying contaminants in aqueous solutions. In one embodiment, an apparatus for the detection of contaminants within a liquid comprises a sensor and a controller. The sensor comprises a film and a transducer configured such that, during use, a first surface of the transducer is in fluid communication with a liquid, and the film is disposed between the first surface and the liquid. The film can be a polymeric material capable of hindering the transport of a non-desired species therethrough. The controller is in operational communication to the transducer, and is configured to determine the concentration of contaminants within the liquid.
    Type: Application
    Filed: November 16, 2006
    Publication date: May 10, 2012
    Inventors: Radislav Alexandrovich Potyrailo, David James Monk, Ryo Tamaki
  • Patent number: 8116421
    Abstract: An apparatus for inspecting and testing a startup range neutron monitoring system for a nuclear reactor. The apparatus includes: a neutron-flux detector; a preamplifier that amplifies an electric signal output from the neutron-flux detector; a pulse measurement unit that counts times when electric signal output from the preamplifier exceeds a discrimination voltage; a discrimination-voltage setting unit that applies the discrimination voltage to the pulse measurement unit; a voltage-setting unit that applies a voltage to the neutron-flux detector; an arithmetic processing unit that calculates an output power of the reactor based upon an output signal of the pulse measurement unit; an output unit that outputs data representing the output power of the reactor, calculated by the arithmetic processing unit; and an inspecting/testing unit that sets the discrimination voltage and the voltage to be applied by the voltage-setting unit.
    Type: Grant
    Filed: June 10, 2008
    Date of Patent: February 14, 2012
    Assignee: Kabushiki Kaisha Toshiba
    Inventor: Hideyuki Kitazono
  • Publication number: 20120033779
    Abstract: A method of determining in-reactor susceptibility of a zirconium-based alloy to shadow corrosion according to a non-limiting embodiment of the present invention may include immersing a first electrode and a second electrode in an electrolytic solution. The first electrode may be formed of the zirconium-based alloy, while the second electrode may be formed of a metallic material suitable for use in a nuclear reactor and having a higher electrochemical corrosion potential than the zirconium-based alloy. The method may additionally include irradiating the immersed first and second electrodes with electromagnetic radiation. A galvanic current may then be measured between the first electrode and the second electrode to ascertain the relative in-reactor susceptibility of the zirconium-based alloy to shadow corrosion. The present invention allows a simplified and more rapid method of developing solutions that mitigate shadow corrosion, thereby potentially saving years of expensive in-reactor testing.
    Type: Application
    Filed: August 4, 2010
    Publication date: February 9, 2012
    Applicant: GLOBAL NUCLEAR FUEL - AMERICAS, LLC
    Inventors: Daniel Reese Lutz, Young Jin Kim, Yang-Pi Lin
  • Publication number: 20110150162
    Abstract: Provided is an automated periodic surveillance testing method and apparatus in a digital reactor protection system, which unites a passive testing means such as a self-diagnosis or an on-line state comparison with an active testing means such as an automatic logic test and the like in the digital reactor protection system. Accordingly, a device self-diagnosis, an on-line state diagnosis, and an automatic logic test are used as the automated periodic surveillance testing method in the digital reactor protection system. Thus, the time consumed in a periodic surveillance test can be minimized, thereby saving reactor operating costs, and excessive manpower can be avoided, thereby decreasing potential human errors. Also, a channel detour time at which one of multiple channels is detoured can be minimized based on the automated periodic surveillance test in the digital reactor protection system, thereby enhancing stability.
    Type: Application
    Filed: December 7, 2010
    Publication date: June 23, 2011
    Inventors: Seop Hur, Inkoo Hwang, Dong-Hoon Kim, Jung Taek Kim, Jong-Gyun Choi, Jung-Woon Lee, Gee Yong Park, Jae-Chang Park, Dong-Young Lee, Kee-Choon Kwon
  • Patent number: 7953503
    Abstract: A method for operating a process plant, in which a number of alarm notifications for indicating non-compliant operating events of the process plant are generated at process level. Alarm notifications which can be generated during the operation of the process plant are defined. At least a number of the generatable alarm notifications are assigned, in each case at least a first value or a second value as a dependency value. A current process state of the process plant is determined and depending on the determined process state, those alarm notifications to which the first value was assigned as a dependency value are not indicated.
    Type: Grant
    Filed: January 22, 2008
    Date of Patent: May 31, 2011
    Assignee: Siemens Aktiengesellschaft
    Inventor: Oliver Thurau
  • Publication number: 20100254505
    Abstract: An apparatus may include two or more electrical conductors, one or more signal devices, and an analyzer. The one or more signal devices may be adapted to apply one or more signals to the two or more electrical conductors and receive one or more signals from the two or more electrical conductors. The analyzer may be adapted to determine power level in the nuclear reactor using at least one of the applied signals and at least one of the received signals. A method of determining power level in a nuclear reactor may include: measuring impedance values of two or more electrical conductors disposed in the nuclear reactor and using the measured impedance values to determine the power level. A method of operating a nuclear reactor may include: measuring the impedance values and using the measured impedance values to determine parameters of the nuclear reactor.
    Type: Application
    Filed: April 1, 2009
    Publication date: October 7, 2010
    Inventor: William Francis Splichal, JR.
  • Publication number: 20100246741
    Abstract: There are provided a first display that displays a system diagram of a safety system and makes it possible to select a symbol indicating a safety-system plant equipment included in the system diagram; a second display that displays an operating device for operating the safety-system plant equipment and makes it possible to operate the operating device; and a safety system display control device that outputs the system diagram to be displayed on the first display, outputs on the second display an operating device corresponding to a symbol that is included in the system diagram and is selected by means of the first display, and converts operation of the operating device performed on the second display into a signal that is outputted to the safety-system plant equipment.
    Type: Application
    Filed: July 31, 2009
    Publication date: September 30, 2010
    Applicant: Mitsubishi Electric Corporation
    Inventor: Yasuyuki NISHIJIMA