Plural Sensed Different Conditions Or Measured Variables Correlated Patents (Class 376/216)
  • Patent number: 10360093
    Abstract: The state of a system is determined in which data sets are generated that include a plurality of data instances representing states of one or more components of a computer system. The data instances generated by one or more data set sources that are configured to output a data instance in response to a trigger associated with the one or more components. The data instances are normalized by the application of one or more rules. The data instances from individual data set sources are separately collated to generate groups of time-specific collated data instances. State types may be assigned to each of the collated data instance groups. Distributions of state-types across the groups may be determined and a list of infrequent state-types may be generated based on the determined distributions of state-types across the groups.
    Type: Grant
    Filed: November 18, 2015
    Date of Patent: July 23, 2019
    Assignee: Fair Isaac Corporation
    Inventors: Shafi Ur Rahman, Ashish Gupta
  • Patent number: 10304104
    Abstract: An information processing apparatus includes a detection unit that detects an orientation of the face of a customer in a store, an estimating unit that estimates the customer's state of mind in accordance with a chronological change of the detected orientation of the face of the customer, and an output unit that outputs guidance information that guides the customer to a customer service, in accordance with the estimated customer's state of mind.
    Type: Grant
    Filed: August 8, 2016
    Date of Patent: May 28, 2019
    Assignee: FUJI XEROX CO., LTD.
    Inventors: Yusuke Yamaura, Takeshi Onishi, Masatsugu Tonoike, Jun Shingu, Daisuke Ikeda, Yusuke Uno
  • Patent number: 10222791
    Abstract: An operator of a nuclear plant is provided with an action margin time up to the execution of a next action to be performed in response to a detected accident based on sensor signals received from sensors for the plant. The operator is provided with a displayed graph showing the received sensor signals, estimated sensor signals for the future, the action margin time and an action threshold value corresponding to the next action. Accordingly, the operator can readily grasp how much time is available to perform the next action before the received sensor signals are predicted to exceed the action threshold value.
    Type: Grant
    Filed: April 4, 2014
    Date of Patent: March 5, 2019
    Assignee: Hitachi, Ltd.
    Inventors: Masaki Kanada, Setsuo Arita, Yoshihiko Ishii, Kenichi Katono, Tadaaki Ishikawa, Ryota Kamoshida
  • Patent number: 10209109
    Abstract: A nuclear flowmeter for measurements in multiphase flows consisting of up to three main phases that is connected in series in the output flow in a production line of an oil well, that includes a “U” shaped arrangement formed by an input branch and an output branch placed at both sides of the “U” shaped arrangement, where the input branch is connected to the production line of the oil well through an input pipe section (1) and the output branch is connected to the line of production of the oil well through an output pipe section (21) placed respectively at both ends of the “U” shaped arrangement; the input branch includes a pipe section with section reduction that forms a Venturi (3) while in the output branch includes a pipe section with possible section reduction (5) where the nuclear measurements are made, is provided.
    Type: Grant
    Filed: September 27, 2017
    Date of Patent: February 19, 2019
    Inventors: Juan Bautista Emanuel Gimenez, Miguel Ángel Nicolás Gimenez
  • Patent number: 10163532
    Abstract: A system for controlling the power level of a natural circulation boiling water nuclear reactor (NCBWR) may include a heating subsystem for heating feedwater flowing into an annulus of the NCBWR to increase the temperature of recirculation water flowing through the core above a predetermined recirculation water operating temperature. Additionally the system may include a temperature sensor operable to sense the temperature of the feedwater flowing into the annulus. The temperature sensor is communicatively connected to a temperature controller operable to command the heating subsystem to increase the temperature of the feedwater flowing into the annulus to a requested temperature above a predetermined operating temperature of the feedwater flowing into the annulus.
    Type: Grant
    Filed: April 21, 2014
    Date of Patent: December 25, 2018
    Assignee: GE-HITACHI NUCLEAR ENERGY AMERICAS LLC
    Inventors: Stephan Craig Moen, Jack Patrick Noonan, Pradip Saha
  • Patent number: 10147220
    Abstract: A computer-implemented method includes accessing a plurality of sets of outputs for an interactive animation, with each set of outputs being associated with a different sequence of a plurality of sequences of discrete control inputs, and with each set of outputs comprising an output that provides a stored portion of the animation; and transmitting, to a client device, information indicative of at least one of the plurality of sets of outputs for the animation and the output that provides the stored portion of the animation, which when rendered by the client device causes the animation to be presented to a user.
    Type: Grant
    Filed: March 13, 2015
    Date of Patent: December 4, 2018
    Assignee: Carnegie Mellon University
    Inventors: Matthew Stanton, Adrien Treuille, Kayvon Fatahalian, James O'Brien, Ben Humberston, Brandon Kase
  • Patent number: 9997265
    Abstract: A safety system for a nuclear power plant includes first through fourth sensors; a first division, including a first calculation module that determines first and second calculation results based on signals from the first and second sensors, a first data-sharing module for sharing the first and second calculation results with a second division, and a first voting logic for generating a first safety demand signal based on the first through fourth calculation results; and the second division, including a second calculation module for determining the third and fourth calculation results based on signals from the third and fourth sensors, a second data-sharing module for sharing the third and fourth calculation results with the first division, and a second voting logic for generating a second safety demand signal based on the first, second, third, and fourth calculation results, wherein the first through fourth sensors each monitor the same plant parameters.
    Type: Grant
    Filed: March 27, 2015
    Date of Patent: June 12, 2018
    Assignee: Mitsubishi Electric Power Products, Inc.
    Inventors: Gilbert William Remley, Kenneth Scarola
  • Patent number: 9842663
    Abstract: A core monitoring system including: a TIP measuring a neutron amount in a nuclear reactor; a TIP drive device; a TIP panel; a neutron monitoring panel; and a process computer. The TIP panel includes: a TIP level processor and a TIP position processor that process a TIP level signal and a TIP position signal input from the TIP drive device, respectively; a time setting section synchronizing the TIP level signal and the TIP position signal; and a TIP level data storage section storing synchronized TIP level data. The neutron monitoring panel includes a time setting section setting collecting time of a LPRM level signal and an APRM level signal. The process computer compares the time and stores the TIP level data from the TIP panel and the LPRM and APRM level signals from the neutron monitoring panel corresponding in time, and calculates core performance based on the TIP level data.
    Type: Grant
    Filed: December 21, 2011
    Date of Patent: December 12, 2017
    Assignee: Kabushiki Kaisha Toshiba
    Inventors: Masayuki Okada, Atsuhiko Koizumi
  • Patent number: 9842300
    Abstract: For calculating statistical Markov model-like state transition probabilities, a method represents state transition probabilities between a plurality of statistical Markov model-like states and output probabilities associated with a plurality of previous statistical Markov model-like states. The state transition probabilities between the plurality of previous states depend on a sequence of previous states of the plurality of previous states. The output probabilities associated with each of the plurality of states depend on the sequence of previous states.
    Type: Grant
    Filed: November 4, 2014
    Date of Patent: December 12, 2017
    Assignee: Utah State University
    Inventors: Todd K. Moon, Jacob H. Gunther
  • Patent number: 9819555
    Abstract: An object of the present invention is to assist in describing policies so that errors when describing policies are reduced.
    Type: Grant
    Filed: February 15, 2012
    Date of Patent: November 14, 2017
    Assignee: NEC Corporation
    Inventor: Nobuyuki Tomizawa
  • Patent number: 9784138
    Abstract: A waste heat power generation device having: an evaporator that recovers waste heat energy to evaporate a working medium; an expansion turbine generator that generates electric power with the working medium being supplied from the evaporator; a condenser that condenses the working medium discharged from the expansion turbine generator; a pump that feeds the working medium condensed in the condenser toward the evaporator; a measuring device that measures the amount of power generated by the expansion turbine generator per unit time; and a control device that controls the driving of the pump based on the measurement result of the measuring device.
    Type: Grant
    Filed: May 12, 2015
    Date of Patent: October 10, 2017
    Assignee: IHI CORPORATION
    Inventors: Toshio Takahashi, Hirohisa Wakisaka, Kouichi Machida
  • Patent number: 9495717
    Abstract: A Plant safety design assistance device (100) is configured by a communication device (140), a diagnostics and monitoring device (110), a fault inspection management device (120), and a design and manufacturing device (130) being interconnected via network (150). The diagnostics and monitoring device (110) receives plant status information (dc) from a plant control system (1) and carries out monitoring and diagnostics an the plant. The fault inspection management device (120) maintains fault inspection information (D2) of an apparatus which is used in the plant. The design and manufacturing device (130) maintains design and manufacturing information of the apparatus which is used in the plant. The design and manufacturing devise (130) receives the fault inspection information (D2) from the fault inspection management device (120), and carries out a plant safety design which takes the fault inspection information into account.
    Type: Grant
    Filed: August 25, 2011
    Date of Patent: November 15, 2016
    Assignee: MITSUBISHI HEAVY INDUSTRIES, LTD.
    Inventors: Fumikado Anzai, Kenichi Morimoto, Yoshikane Yamanaka
  • Patent number: 9472116
    Abstract: One embodiment includes a computer-implemented method and system in a network environment using at least a display and a detached sensor. Another embodiment includes a computer-implemented system helping a user learn using a detached imaging sensor. In yet another embodiment, a computer-implemented system monitors automatically more than once a user's behavior while the user is working on materials. Through monitoring the user's voluntary or involuntary behavior, the system determines what to present by the display. The presentation could include providing rewards, punishments, stimulation, and other materials. The system can also react by asking the user a question. Based on the user's response, the system may change to more appropriate materials, or different presentation styles.
    Type: Grant
    Filed: December 21, 2015
    Date of Patent: October 18, 2016
    Assignee: IPLEARN-FOCUS, LLC
    Inventors: Chi Fai Ho, Peter P. Tong
  • Patent number: 9424376
    Abstract: Illustrative embodiments provide for the operation and simulation of the operation of fission reactors, including the movement of materials within reactors. Illustrative embodiments and aspects include, without limitation, nuclear fission reactors and reactor modules, including modular nuclear fission reactors and reactor modules, nuclear fission deflagration wave reactors and reactor modules, modular nuclear fission deflagration wave reactors and modules, methods of operating nuclear reactors and modules including the aforementioned, methods of simulating operating nuclear reactors and modules including the aforementioned, and the like.
    Type: Grant
    Filed: November 15, 2012
    Date of Patent: August 23, 2016
    Assignee: TerraPower, LLC
    Inventors: Jesse R. Cheatham, III, Robert C. Petroski, Nicholas W. Touran, Charles Whitmer
  • Patent number: 9367064
    Abstract: A method in an industrial safety system for controlling a process or equipment. An industrial safety system comprises components with safety devices wherein the safety system enables signals to be generated as a result of an event or alarm. The method and system uses a cause and effect matrix with automated links between each event or alarm and an effect or an action to be taken upon receipt of the event or alarm signal due to the event. In an online view of the improved cause and effect matrix, at least one effect cell of the cause and effect matrix is arranged with a first executable link for a device represented by the at least one effect cell.
    Type: Grant
    Filed: January 25, 2013
    Date of Patent: June 14, 2016
    Assignee: ABB AS
    Inventors: Katharina Gohr, Phillip Weemes
  • Patent number: 9223309
    Abstract: A monitoring apparatus has: an abnormality detecting unit which can detect an abnormality of a self apparatus; a second communication unit for receiving state information through a second communication network; a plant information forming unit for forming plant information as information regarding the whole plant equipment based on a plurality of state information; a first communication unit for transmitting the plant information to a maintenance tool through a first communication network; and an abnormal-case control unit constructed in such a manner that when the abnormality detecting unit detects the abnormality, a substituting request is transmitted to the other control unit, when a response to the substituting request is affirmative, an operation of the self apparatus is stopped, and when the response to the substituting request is negative or when the response to the substituting request is not received, the state information is transferred to the maintenance tool.
    Type: Grant
    Filed: January 30, 2013
    Date of Patent: December 29, 2015
    Assignee: Hitachi, Ltd.
    Inventors: Takahiro Yamada, Yoshio Maruyama, Tohru Akatsu
  • Patent number: 9188104
    Abstract: A LIDAR or other remote sensing apparatus is mounted on a wind turbine to sense one or more wind parameters. An extreme event detector processing signals from the LIDAR to determine whether a given sensed parameter will, when it arrives at the turbine, exceed a predetermined value and represent an extreme event. On detection of an extreme event, the detector outputs an extreme event signal to a controller. The controller controls overrating of the turbine in response to a variety of sensed parameters and selectively operates the turbine at above rated wind speed. On receipt of the extreme event signal the overrating is overridden to prevent damage to turbine components. The controller may be a power plant controller and the override signal may override only over-rating at the turbine which has detected the extreme event, or a plurality of turbines.
    Type: Grant
    Filed: June 26, 2012
    Date of Patent: November 17, 2015
    Assignee: Vestas Wind Systems A/S
    Inventors: Robert Bowyer, Christopher Palmer, Chris Spruce
  • Patent number: 9164647
    Abstract: A graphical user interface device includes an operation procedure information database, a display element information database, an operation determination section, a display element selection section, and an integrated procedure and display-element screen preparation section. Procedure information and a display item to be operated by an operator are registered in the operation procedure information database. The procedure information is text information forming an operation manual. The operation determination section determines a current operation step based on information given from an actual plant. The integrated procedure and display-element screen preparation section prepares a layout of an operation screen allowing the procedure information and the display item of the current operation step to be simultaneously displayed on a single screen of the input/output equipment.
    Type: Grant
    Filed: June 15, 2011
    Date of Patent: October 20, 2015
    Assignee: Mitsubishi Electric Corporation
    Inventors: Yohei Ueno, Tadashi Oi, Kazuyuki Mori, Akira Kobashi
  • Patent number: 9123218
    Abstract: A fire control panel in which an address map window (30), in which terminal device control switches (31) each indicating an address number (AD) of a terminal device are arranged in a matrix shape, is displayed on a display/operation unit (2). In addition, each of the terminal device control switches (31) corresponding to a status stored in a terminal database (DB) is displayed in a display mode that differs depending on each status. Accordingly, it is possible to grasp status information on a large number of terminal devices at a glance through one screen.
    Type: Grant
    Filed: July 5, 2013
    Date of Patent: September 1, 2015
    Assignee: NOHMI BOSAI, LTD.
    Inventors: Katsuhide Tsubokawa, Masahiro Hagita
  • Patent number: 9058028
    Abstract: Systems and methods for adaptive control are disclosed. The systems and methods can control uncertain dynamic systems. The control system can comprise a controller that employs a parameter dependent Riccati equation. The controller can produce a response that causes the state of the system to remain bounded. The control system can control both minimum phase and non-minimum phase systems. The control system can augment an existing, non-adaptive control design without modifying the gains employed in that design. The control system can also avoid the use of high gains in both the observer design and the adaptive control law.
    Type: Grant
    Filed: April 30, 2012
    Date of Patent: June 16, 2015
    Assignee: Georgia Tech Research Corporation
    Inventors: Kilsoo Kim, Tansel Yucelen, Anthony J. Calise
  • Patent number: 8995601
    Abstract: An axial power distribution control device includes an axial offset calculation unit 52, a parameter calculation unit 53, and an axial offset determining unit 55. The axial offset determining unit 55 predicts whether a core axial offset of the power distribution is increased or decreased after a current time, based on a major axis of an ellipse drawn by the xenon parameter and the iodine parameter calculated by the parameter calculation unit 53 and the xenon parameter and the iodine parameter at the current time. This makes it possible to predict a change of the axial offset of the power distribution of a reactor for suppressing a xenon oscillation in the reactor.
    Type: Grant
    Filed: February 18, 2010
    Date of Patent: March 31, 2015
    Assignee: Mitsubishi Heavy Industries, Ltd.
    Inventors: Masayuki Kauchi, Masatoshi Nagai
  • Patent number: 8983810
    Abstract: An apparatus for monitoring nuclear thermal hydraulic stability of a nuclear reactor, contains: a calculation unit configured to calculate a stability index of a nuclear thermal hydraulic phenomenon based on nuclear instrumentation signals, the signals being outputted by a plurality of nuclear instrumentation detectors placed at regular intervals in a reactor core; a simulation unit configured to simulate the nuclear thermal hydraulic phenomenon based on a physical model by using information on an operating state of the nuclear reactor as an input condition; a limit value updating unit configured to update a limit value of the nuclear thermal hydraulic phenomenon based on a result of the simulation; and a determination unit configured to determine, based on the stability index and the limit value, whether or not to activate a power oscillation suppressing device.
    Type: Grant
    Filed: July 6, 2012
    Date of Patent: March 17, 2015
    Assignee: Kabushiki Kaisha Toshiba
    Inventors: Yutaka Takeuchi, Hiroyuki Takeuchi, Kazuki Yano
  • Patent number: 8792604
    Abstract: To predict xenon oscillation at the present time and later. For this purpose, as an axial offset of a power distribution of a reactor is represented by AOp, an axial offset of a power distribution based on xenon distribution is represented by AOx, and an axial offset of a power distribution based on an iodine distribution is represented by AOi, a parameter DAOpx(=AOp?AOx) and a parameter DAOix(=AOi?AOx) are described by a relational expression of a trigonometric function and an exponential function using an angular frequency of xenon oscillation. Next, phases with respect to initial values of the parameters DAOpx and DAOix are obtained (Step S101). The parameter DAOpx and the parameter DAOix expressed by the obtained phase and a coefficient of the relational expression obtained from this phase are plotted on an X coordinate and a Y coordinate, respectively.
    Type: Grant
    Filed: April 30, 2008
    Date of Patent: July 29, 2014
    Assignee: Mitsubishi Heavy Industries, Ltd.
    Inventor: Yoichiro Shimazu
  • Patent number: 8699653
    Abstract: A control strategy for a pressurized water nuclear reactor that employs separate, independent control rod banks for respectively controlling Tavg and axial offset within corresponding deadbands. The strategy does not permit the control banks controlling reactor core power and the control banks controlling axial offset to move together, but normally gives preference to the control banks controlling the Tavg except when a demand signal is received simultaneously by both independent control rod banks to move in a same direction, in which case, the control bank compensating for the axial offset is given preference.
    Type: Grant
    Filed: October 24, 2011
    Date of Patent: April 15, 2014
    Assignee: Westinghouse Electric Company, LLC
    Inventors: Keith J. Drudy, Norman P. Mueller, Elijah A. Richter
  • Patent number: 8656301
    Abstract: An information display system (10) comprises computing hardware (30) coupled to a graphical screen interface. (50) The system (10) further includes one or more interface modules (70) including local data processing thereat for receiving input data streams (S1 to SN). Moreover, the computing hardware (30) is operable to execute one or more software products for generating a software environment presented in operation on the graphical screen interface (50). Furthermore, the computing hardware (30) is operable when executing the one or more software products to present a representation of one or more of the input data streams (S1 to SN) in one or more graphical windows (100, 110, 120A to 120F) within the software environment as provided on the graphical screen interface (50).
    Type: Grant
    Filed: April 30, 2009
    Date of Patent: February 18, 2014
    Assignee: Epsis AS
    Inventors: Jan-Erik Nordtvedt, Jørgen Hosøy
  • Patent number: 8654916
    Abstract: The invention relates to a method for regulation of operational parameters of the core of a pressurised water nuclear reactor comprising: a step of acquisition of values (FH, FB, TBC, TBF, Q) which are representative of the conditions of operating of the core of the reactor; a step of evaluation of the actual values (Tmoye, AOe, {circumflex over (P)} maxe) of the operational parameters at least according to the values acquired (FH, FB, TBC, TBF, Q); a step of selection of a control law for the concentration of a neutron-absorbent component ([B]) and for the positions of insertion (Z1 to Z5) of the groups (P1 to P5) of rods selected from at least the first and second control laws which are different from one another; and a step of regulation of the operational parameters by means of the control law selected, according to set points (Tmoyc, AOc, {circumflex over (P)} maxc) relative to the said parameters and to the actual values (Tmoye, AOe, {circumflex over (P)} maxe) evaluated.
    Type: Grant
    Filed: May 21, 2007
    Date of Patent: February 18, 2014
    Assignee: Areva NP
    Inventor: Alain Grossetete
  • Publication number: 20130315362
    Abstract: A nuclear instrumentation and control system, comprising: an input module, receiving analog inputs from sensors and digital signals from hardware switches; a dual redundant bi-stable processor, connecting to the input module; a dual redundant local coincidence logic processor, connecting to the dual redundant b0-stable processor; an output module, connecting to the dual redundant local coincidence logic processor; an integrated communication processor, connecting to the dual redundant bi-stable processor and the dual redundant local coincidence logic processor; an interface and test panel, connecting to the dual redundant bi-stable processor, the dual redundant local coincidence logic processor and the integrated communication processor; and a video display unit, connecting to the dual redundant bi-stable processor, the dual redundant local coincidence logic processor, the integrated communication processor and the interface and test panel.
    Type: Application
    Filed: May 25, 2012
    Publication date: November 28, 2013
    Applicant: Institute of Nuclear Energy Research Atomic Energy Council, Executive Yuan
    Inventor: TING-CHIA OU
  • Publication number: 20130301772
    Abstract: The object of the present invention is to provide a risk monitoring device and a risk monitoring method for use with a nuclear power facility, providing continuous determination of risk associated with the nuclear power facility, based on one-type security model, which can be implemented using simple software and hardware means.
    Type: Application
    Filed: March 28, 2013
    Publication date: November 14, 2013
    Inventors: Mikhail Evgenievich Fedosovsky, Vadim Igorevich Dunaev, Aleksandr Evgenievich Sherstobitov, Sergey Andreevich Aleksanin, Aleksandr Aleksandrovich Syrov, Vasiliy Ivanovich Gumenyuk
  • Publication number: 20130294560
    Abstract: A reactor control interface includes a home screen video display unit (VDU) displaying blocks representing functional components of a nuclear power plant and connecting arrows that connect blocks that are providing the current heat sinking path for the nuclear power plant. Directions of the connecting arrows represent the direction of heat flow along the current heat sinking path. If the current heat flow path of the plant changes, the connecting arrows are updated accordingly. Additional VDUs include: a mimic VDU displaying a mimic of a plant component; a procedures VDU displaying a stored procedure executable by the plant; a multi-trend VDU trending various plant data; and an alarms VDU displaying side-by-side alarms registries sorted by time and priority respectively. If a VDU fails, the displays are shifted to free up one VDU to present the display of the failed VDU, and one display is shifted to an additional VDU.
    Type: Application
    Filed: April 11, 2013
    Publication date: November 7, 2013
    Inventor: Thomas G. GRAHAM
  • Patent number: 8553829
    Abstract: The invention is principally directed to a reduced order model, XEDOR, facilitating the prediction of and the diagnostics of pellet-clad interaction stress-corrosion-cracking failure of nuclear fuel rods. The invention more particularly relates to assessment of susceptibility to PCI failure for guidance in the design of fuel loading in nuclear reactors. The invention additionally relates to the protection against PCI failure by providing operational information to operators of a nuclear reactor during power maneuvering, including predictive calculations prior to executing power maneuvers. Additionally, the invention relates to the diagnostics of an event suggesting a possible PCI cladding failure.
    Type: Grant
    Filed: September 26, 2007
    Date of Patent: October 8, 2013
    Assignee: Areva NP SAS
    Inventor: Yousef Farawila
  • Patent number: 8467491
    Abstract: The feedwater controller of a nuclear power plant having three or more feedwater pumps supplying water to the reactor vessel, electric motors driving the feedwater pumps and electric power converters connected to the electric motors is equipped with a flow rate controller and a trip compensation means. The flow rate controller calculates a flow rate to the reactor vessel based on a detected value indicating a condition of the nuclear power plant and a preset value of the water level of the reactor vessel, and generates a rotation speed command signal for the electric motors based on the flow rate command signal. The trip compensation means increases the rotation speed of the electric motors not having tripped if one of the feedwater pumps trips.
    Type: Grant
    Filed: July 24, 2007
    Date of Patent: June 18, 2013
    Assignee: Kabushiki Kaisha Toshiba
    Inventor: Shinya Tominaga
  • 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.
  • Publication number: 20120099690
    Abstract: A moderator temperature coefficient measuring device include a control rod driving device; a reactivity measurement processing unit capable of measuring the reactivity of the reactor; an inflow temperature sensor for sensing the inflow temperature of a reactor coolant flowing into the reactor; an outflow temperature sensor for sensing the outflow temperature of the reactor coolant flowing out of the reactor; an average temperature measurement processing unit for measuring the average temperature from the sensed inflow and outflow temperatures; an power control unit for providing control so that the reactor delivers constant thermal power; and a temperature coefficient calculating unit for calculating the temperature coefficient of the reactor coolant based on the amount of change in reactivity between before and after the insertion of the control rod and the amount of change in average temperature between before and after the insertion of the control rod under the constant thermal power.
    Type: Application
    Filed: October 14, 2011
    Publication date: April 26, 2012
    Applicant: MITSUBISHI HEAVY INDUSTRIES, LTD.
    Inventors: Daisuke Sato, Hideki Matsumoto
  • Patent number: 8135106
    Abstract: The present invention provides a method of operating a Boiling Water Reactor, having the steps of analyzing LPRM signals for oscilliatory behavior indicative of neutron-flux-coupled density wave oscillations, determining if oscilliatory behavior is present in the signals; initiating a reactor protective corrective action if the oscilliatory behavior is determined, and in addition, initiating corrective actions if neutron uncoupled oscillations are possible. Detecting the later is performed through analytically determined exclusion zone on the power flow map or by on-line stability calculations for several high power channels.
    Type: Grant
    Filed: April 18, 2005
    Date of Patent: March 13, 2012
    Assignee: Areva NP Inc.
    Inventors: Yousef M. Farawila, Douglas W. Pruitt
  • Patent number: 7945011
    Abstract: The present invention relates to a method of controlling a nuclear reactor during a transient period. The method includes actuating the steam dump system in response to a temperature error signal and a power mismatch signal.
    Type: Grant
    Filed: May 4, 2010
    Date of Patent: May 17, 2011
    Assignee: Westinghouse Electric Company LLC
    Inventors: J. Seenu Srinivasan, Rachel R. Marangoni
  • Patent number: 7860206
    Abstract: In order to provide a reactor power control apparatus which can maintain a stable water level when reactivity control based on control rod operation and water level adjustment is performed, this invention comprises a turbine control which calculates the load set error signal from the error between the set target generator power value and the generator power that was fed back and outputs to the turbine control apparatus; control rod control in the natural circulation boiling water reactor which calculates the control rod operation signal and outputs it to the control rod drive control apparatus; water level control inside the natural circulation boiling water reactor which calculates the water level set signal and outputs it to the feed water control apparatus; and the switch determining device which selectively outputs one of the control rod control and water level control based on the generator power that was fed back, the reactor power and water level, as well as switching rules and determination values.
    Type: Grant
    Filed: January 25, 2007
    Date of Patent: December 28, 2010
    Assignee: Hitachi-GE Nuclear Energy, Ltd.
    Inventors: Atsushi Fushimi, Setsuo Arita, Kazuhiko Ishiii, Yoshihiko Ishii, Shin Hasegawa, Atsutoshi Mizuide
  • Patent number: 7742555
    Abstract: The present invention relates to a method of controlling a nuclear reactor during a transient period. The method includes actuating the steam dump system in response to a temperature error signal and a power mismatch signal.
    Type: Grant
    Filed: July 14, 2008
    Date of Patent: June 22, 2010
    Assignee: Westinghouse Electric Company LLC
    Inventors: Seenu J. Srinivasan, Rachel R. Marangoni
  • Publication number: 20100119026
    Abstract: A method determines a volumetric power distribution of a core of a nuclear reactor using a set of detectors for measuring a neutronic flow provided outside the reactor vessel, and a set of probes for measuring the temperature of the coolant at the outlet of the fuel assemblies. The method comprises the step of determining a first volumetric power distribution using a neutronic calculation code instantaneously solving the diffusion equation and updating the isotopic balance of the core during the fuel depletion based on values of the core operation parameters, and the step of determining a new volumetric power distribution by adjusting the first volumetric power distribution using the measures provided by the sensors for measuring the neutronic flow and provided outside the reactor vessel and by the temperature measuring probes.
    Type: Application
    Filed: March 14, 2008
    Publication date: May 13, 2010
    Inventors: Antoine Gautier, David Durey
  • Patent number: 7693249
    Abstract: The method of improving nuclear reactor performance involves generating an operational solution for a nuclear reactor based on a constraint accounting for a problem with operation of the nuclear reactor. The generated operational solution can then be implemented at the nuclear reactor.
    Type: Grant
    Filed: January 31, 2003
    Date of Patent: April 6, 2010
    Assignee: Global Nuclear Fuel - Americas, LLC
    Inventors: David Joseph Kropaczek, William Earl Russell, II
  • Patent number: 7555092
    Abstract: A system and method is provided for a continual updating of the optimization of multiple operational control-variables during the operation of a nuclear reactor over a plurality of fuel cycles. A networked computer system includes one or more hosts programmed to execute an optimization process to identify and make changes in quantitative values of operational control-variables that result in improved efficiency and operational flexibility. Optimization and updating of operational control-variables may proceed selectively under manual control for inputting specific optimization constraints and reactor state-point information or may proceed autonomously through a repetitive performing of the optimization process based upon a predetermined user-defined strategy stored on the network.
    Type: Grant
    Filed: June 30, 2003
    Date of Patent: June 30, 2009
    Assignee: General Electric Company
    Inventors: William Earl Russell, II, David Joseph Kropaczek, Glen Alan Watford
  • Publication number: 20090161810
    Abstract: In the present invention, a reactor power control apparatus of a natural circulation reactor comprises a reactor pressure vessel which circulates cooling water using the density difference of the coolant inside, a feed water pipe which is connected to the reactor pressure vessel and supplies cooling water, a power control section which controls the reactor power using a control rod. The feed water pipe has an ultrasonic thermometer sensor. Driving of the control rod is controlled by the power control section based on the feed water temperature detected by the feed water thermometer. The reactor power control apparatus can detect the temperature of the feed water and perform drive control of the control rod preferentially, and obtain stable reactor power.
    Type: Application
    Filed: January 14, 2009
    Publication date: June 25, 2009
    Inventors: Koichi Sato, Shin Hasegawa
  • Patent number: 7532698
    Abstract: Systems and methods for a method for determining a critical effective k at an off-rated core state of a nuclear power plant includes determining, for the off-rated core state a control rod density, a percent core power, a gadolinium reactivity worth, a doppler reactivity worth, and a xenon reactivity worth responsive to a control rod pattern, a reactor power plan including the off-rated core state, and a reference effective k, calculating a change in an effective k from the reference effective k at the off-rated core state responsive to two or more parameters selected from the group consisting of the control rod density, the percent core power, the gadolinium reactivity worth, the doppler reactivity worth, and the xenon reactivity worth, and generating the critical effective k for the off-rated core state responsive to the change in the effective k from the reference effective k.
    Type: Grant
    Filed: November 29, 2006
    Date of Patent: May 12, 2009
    Assignee: Global Nuclear Fuel - Americas, LLC
    Inventors: Ugur Mertyurek, David Joseph Kropaczek, Atul A. Karve, Angelo P. Chopelas
  • Patent number: 7366273
    Abstract: In a method of determining an operating margin to a given operating limit in a nuclear reactor, operational plant data from an on-line nuclear reactor plant is accessed, and reactor operation is simulated off-line using the operational plant data to generate predicted dependent variable data representative of the given operating limit. The predicted dependent variable data is normalized for evaluation with normalized historical dependent variable data from stored operating cycles of plants having a similar plant configuration to the on-line plant. A time-dependent average bias and a time-dependent uncertainty value for the predicted dependent variable data are determined using the normalized historical dependent variable data, and a risk-tolerance level for the on-line plant is obtained.
    Type: Grant
    Filed: December 30, 2005
    Date of Patent: April 29, 2008
    Assignee: General Electric Company
    Inventors: William Earl Russell, II, Russell Morgan Fawcett, William Charles Cline, David Joseph Kropaczek, Glen A. Watford, Lukas Trosman, Steven Barry Sutton, Christian Carlos Oyarzun
  • Publication number: 20070201599
    Abstract: In order to provide a reactor power control apparatus which can maintain a stable water level when reactivity control based on control rod operation and water level adjustment is performed, this invention comprises a turbine control which calculates the load set error signal from the error between the set target generator power value and the generator power that was fed back and outputs to the turbine control apparatus; control rod control in the natural circulation boiling water reactor which calculates the control rod operation signal and outputs it to the control rod drive control apparatus; water level control inside the natural circulation boiling water reactor which calculates the water level set signal and outputs it to the feed water control apparatus; and the switch determining device which selectively outputs one of the control rod control and water level control based on the generator power that was fed back, the reactor power and water level, as well as switching rules and determination values.
    Type: Application
    Filed: January 25, 2007
    Publication date: August 30, 2007
    Inventors: Atsushi Fushimi, Setsuo Arita, Kazuhiko Ishii, Yoshihiko Ishii, Shin Hasegawa, Atsutoshi Mizuide
  • Patent number: 7139355
    Abstract: A method of operating a nuclear power plant includes determining and licensing a maximum power level at which the power plant can be operated subsequent to the beginning of a fuel cycle, and with the power plant being operated at less than its maximum power rating at certain times such as at the beginning of a fuel cycle. The maximum power level is greater than the power level that would be calculated based upon an assumption that the heat flux peaking factor (FQ) and enthalpy rise peaking factor (F?H) remain at their maximum level throughout an entire fuel cycle. The maximum power rating takes advantage of factors such as known reductions in FQ and F?H at certain points in the fuel cycle, the marginal additional capacity of the Balance Of Plant, and the occasional optimization of process parameters such as ultimate heat sink temperature and atmospheric conditions.
    Type: Grant
    Filed: October 2, 2003
    Date of Patent: November 21, 2006
    Assignee: Westinghouse Electric Co, LLC
    Inventor: Robert H. McFetridge
  • Patent number: 6928132
    Abstract: A method for operating a system having a plurality of modes and interlocks between the modes is provided. The method includes operating the system in a first mode and switching the system to a second mode without going to a standby mode.
    Type: Grant
    Filed: December 19, 2001
    Date of Patent: August 9, 2005
    Assignee: General Electric Company
    Inventor: Robert W. Droege
  • Patent number: 6910156
    Abstract: A diagnostic method and system for a technical installation establish the cause of a fault event. A reliable, flexible and simple possible way of diagnosing an installation is provided by placing state variables that characterize an operating state of the technical installation in a dependency tree and establishing a fault path in the dependency tree by linking change directions of diagnostic parameters contained in the dependency tree.
    Type: Grant
    Filed: January 28, 2002
    Date of Patent: June 21, 2005
    Assignee: Siemens Aktiengesellschaft
    Inventor: Gottfried Adam
  • Patent number: 6801885
    Abstract: A method of evaluating a containment building design includes the steps of assembling a first database of test results; selecting models (algorithms) for the design to be evaluated; comparing a first set of test results of the model to test results in the first database of test results; establishing uncertainty boundaries for the first set of test results of the model; assembling a second database of test results; determining whether the test results of the second database are within the uncertainty boundaries of the model; and evaluating an actual or proposed containment building design based upon the model when test results of the second database are within the uncertainty boundary.
    Type: Grant
    Filed: October 3, 2000
    Date of Patent: October 5, 2004
    Assignee: Westinghouse Electric Company LLC
    Inventor: Robert E. Henry
  • Patent number: 6798859
    Abstract: A branch amplifier card for a nuclear reactor control rod drive control system is provided. The control system includes a control processor, a plurality of transponder cards arranged in clusters with each cluster under the control of a branch amplifier card. The branch amplifier card is configured to receive commands from the control processor, send the converted commands to transponder cards under the control of the branch amplifier card and to a downstream branch amplifier card, receive an acknowledge word from transponder cards under the control of the branch amplifier card, add AC voltage threshold level information about the transponder cards under the control of the branch amplifier card to the acknowledge word, permit transponder trouble information attached to the acknowledge word to remain in the acknowledge word, and resend the acknowledge word including the transponder trouble information to an upstream branch amplifier card.
    Type: Grant
    Filed: August 18, 2003
    Date of Patent: September 28, 2004
    Assignee: General Electric Company
    Inventors: William Michael Steiner, Craig Miles Smith, Leonid Boris Sheikman, Craig Ernest Leighty
  • Publication number: 20040071253
    Abstract: A method of operating a nuclear power plant includes determining and licensing a maximum power level at which the power plant can be operated subsequent to the beginning of a fuel cycle, and with the power plant being operated at less than its maximum power rating at certain times such as at the beginning of a fuel cycle. The maximum power level is greater than the power level that would be calculated based upon an assumption that the heat flux peaking factor (FQ) and enthalpy rise peaking factor (F&Dgr;H) remain at their maximum level throughout an entire fuel cycle. The maximum power rating takes advantage of factors such as known reductions in FQ and F&Dgr;H at certain points in the fuel cycle, the marginal additional capacity of the Balance Of Plant, and the occasional optimization of process parameters such as ultimate heat sink temperature and atmospheric conditions.
    Type: Application
    Filed: October 2, 2003
    Publication date: April 15, 2004
    Inventor: Robert H. McFetridge