Abstract: A nuclear reactor (1) includes a vessel (3) has a central axis (X); and a core (5) arranged in the vessel (3). The core (5) includes a plurality of nuclear fuel assemblies, a primary water layer (7) separating the core (5) from the vessel (3) radially from the central axis (X) and surrounding the core (5); and a system (9) for controlling and protecting the nuclear reactor. The control and protection system (9) includes a device (11) for continuously measuring the neutron flux emitted by the core (5). The measuring device (11) includes at least one neutron detector (12) arranged in the primary water layer (7) separating the core (5) from the vessel (3).

Abstract: A method regulates operating parameters comprising at least the mean temperature of the core (Tm), and the axial power (AO) imbalance. The method includes development of a vector (US) of control values of the nuclear reactor by a supervisor (31) implementing a predictive control algorithm; development of a vector (uK) of corrective values of the nuclear reactor controls by a regulator (33) implementing a sequenced gain control algorithm; development of a vector (U) of corrected values of the commands of the nuclear reactor, by using the vector (US) of the values of the commands produced by the supervisor (31) and the vector (uK) of the corrective values of the commands produced by the regulator (33); and regulation of the operating parameters of the nuclear reactor, by controlling actuators using the vector (U) of the corrected values of the controls.

Abstract: A learning computer system may estimate unknown parameters and states of a stochastic or uncertain system having a probability structure. The system may include a data processing system that may include a hardware processor that has a configuration that: receives data; generates random, chaotic, fuzzy, or other numerical perturbations of the data, one or more of the states, or the probability structure; estimates observed and hidden states of the stochastic or uncertain system using the data, the generated perturbations, previous states of the stochastic or uncertain system, or estimated states of the stochastic or uncertain system; and causes perturbations or independent noise to be injected into the data, the states, or the stochastic or uncertain system so as to speed up training or learning of the probability structure and of the system parameters or the states.

Abstract: A method may include receiving data from a computing device requesting approval of a loan application; accessing time-series data associated with the user from a knowledge graph; building a feature vector based on the accessed time-series data; inputting the feature vector into a machine learning model; receiving a response from the output from the machine learning mode, the output indicating a level of approval for the user with respect to the loan application; and transmitting a response to the request based on the level of approval.

Abstract: There is provided a computer-implemented method for duplicating an application state, the method including: recording one or more point-in-time characteristics of an original application state of an application, the recording including: parsing underlying code for the application to identify (i) a set of state variables that together define the original application state and (ii) a set of logical breadcrumbs identifying a pre-determined number of past actions that led to the original application state; establishing one or more logical anchor points based on the set of state variables; provisioning memory resources to support a duplicate application state; on the provisioned memory resources, initiating a copy of the application; transferring the one or more point-in-time characteristics to the provisioned memory resources, the transferring including: configuring the copy of the application using the one or more point-in-time characteristics to regenerate the original application state on the copy of the appli

Abstract: A plant assistance assessment system 100 that assesses a plurality of nuclear power generation plants 110 includes an abnormality sign monitoring system 121 that monitors an abnormality sign in a plant, based on plant data of the nuclear power generation plants; a fault diagnosis system 122 that performs fault diagnosis on each of devices in the plants, based on abnormality sign detection information; a progress prediction system 123 that simulates progress of the plants, based on fault information; an abnormal phenomenon specification system 124 that specifies a potential abnormal phenomenon in the plants, based on progress prediction information; a risk assessment system 125 that assesses a risk of a fault in the devices in the plants in a probabilistic manner; and an abnormal phenomenon assessment system 126 that assesses likelihood of occurrence of an abnormal phenomenon, based on abnormal phenomenon information and fault probability information.

Abstract: A method to determine a global core reactivity bias and the corresponding estimated critical conditions of a nuclear reactor core prior to achieving reactor criticality. The method first requires collection and evaluation of the inverse count rate ratio (ICRR) data; specifically, fitting measured ICRR vs. predicted ICRR data. The global core reactivity bias is then determined as the amount of uniform reactivity adjustment to the prediction that produces an ideal comparison between the measurement and the prediction.

Abstract: A notification device is provided with: an abnormality estimation unit for estimating a state relating to an abnormality of a plant and a factor relating to the abnormality of the plant; an item specifying unit for specifying inspection items on the basis of the abnormality of the plant and the state relating to the factor relating to the abnormality of the plant estimated by the abnormality estimation unit; a notification unit for notifying of the inspection items specified by the item specifying unit; a stop-time item specifying unit for specifying the inspection items which should be checked at a time of a stop out of the inspection items specified by the item specifying unit; a check result acquisition unit for receiving a check result for the inspection items notified of by the notification unit; and a stop-time item output unit for outputting the inspection items which should be checked at the time of stop.

Abstract: A nuclear-power-plant computer-based procedure display device is disposed in a main control room of a nuclear power plant, and includes a operating procedure storage unit that stores a computer-based procedure in which plant operation procedures of the nuclear power plant are divided into procedure steps and listed, a operating procedure display unit that displays the computer-based procedure, and a operating procedure display control unit that controls display of the computer-based procedure. In a case where the procedure step displayed on the operating procedure display unit is selected by an operator, the operating procedure display control unit displays an indication that the procedure step is selected, on the operating procedure display unit.

Abstract: Systems and methods for an automated hardware-in-the-loop tester are disclosed and include a processor configured to execute instructions stored in a nontransitory computer-readable medium. The instructions include executing an executable object, which includes identifying a first circuit from at least one circuit based on the executable object. The instructions include, in response to identifying the first circuit, controlling a first signal transmitted from the first circuit to an electronic control unit (ECU). The first signal represents one of (i) a signal transmitted by a vehicle and (ii) a signal received from a communications system. While transmitting the first signal, the instructions include generating a first set of data that indicates operating characteristics of the ECU in response to receiving the first signal. The instructions include generating a report based on the first set of data.

Abstract: A system for monitoring fissile material contents inside of a nuclear reactor can include at least a first neutron detector positioned outside a radiation shield and configured to detect a plurality of neutrons originating from the reactor core and having passed through the radiation shield, and configured to generate a first output signal, and a controller communicably linked to the first neutron detector to receive the first output signal and a power output of the nuclear reactor.

Abstract: A method of developing and managing a training program is provided. The method includes defining the training program from a plurality of parameters, defining a desired outcome of the training program for at least one learner, and determining a predicted outcome for the training program for the at least one learner. The predicted outcome is determined based on actual performance data for the plurality of parameters for the at least one learner. The method also includes adjusting the plurality of parameters of the training program if a difference between the desired outcome and the predicted outcome is greater than a predetermined threshold.

Abstract: An operation and observation system of a technical plant and/or a technical process and associated method are provided for operating components and for displaying measurement readings, process variables and/or status messages of the components of the plant and/or process. The system includes at least one large screen for displaying the components of the technical process and/or technical plant, and a plurality of operator workstations. A movement detection and movement control component is installed on the screen and on the operator workstations, which allows an operation and/or polling of the components, the measurement readings, the process variables and/or the status messages of the components of the technical plant or of the technical process by means of a body movement of an operator.

Abstract: An apparatus includes an image capturing device, a display, a storage, and a controller. In the storage, for an alarm window having plural lit portions that indicate alarms for plural items by lighting, position information and procedure information are stored beforehand, the position information associating a layout of the lit portions, with the respective items, the procedure information being handling procedures for the respective items corresponding to the respective lit portions. The controller displays the alarm window image-captured by the image capturing device on the display, causes an on-display position of any of the lit portions that has been lit to be selectable, and if the on-display position of the lit portion that has been lit is selected, reads out procedure information of the item corresponding to the lit portion from the storage and displays the procedure information on the display.

Abstract: Exemplary embodiments relate to systems for building a model of changes to data items when information the data items is limited or not directly observed. Exemplary embodiments allow properties of the data items to be inferred using a single data structure and creates a highly granular log of changes to the data item. Using this data structure, the time-varying nature of changes to the data item can be determined. The data structure may be used to identify characteristics associated with a regularly-performed action, to examine how adherence to the action affects a system, and to identify outcomes of non-adherence. Fungible data items may be mapped to a remediable condition or remedy class. This may be accomplished by automatically deriving conditions and remedial information from available information, matching the conditions to remedial classes or types via a customizable mapping, and then calculating adherence for the condition on the available information.

Abstract: Methods and systems for infrastructure-monitoring control are provided. An example method for providing a visual representation of system events occurring in a system monitored by an infrastructure-monitoring control system includes the infrastructure-monitoring control system providing, in substantially real-time, a visual representation of at least one system event occurring in the system, wherein the visual representation comprises a color-coded visual representation depicting the at least one system event throughout the system. The method further includes the infrastructure-monitoring control system storing the visual representation. Still further, the method includes the infrastructure-monitoring control system then providing the visual representation after a given amount of time since the at least one system event.

Abstract: Techniques for visual configuration and activation are described. Techniques discussed herein enable visuals to be presented to a user based on a user-specific visual configuration. The visuals are activated such that the visuals are selectable to access various functionalities. In at least some embodiments, a visualization that represents a user-specific visual configuration is provided to and displayed on a device. The visualization includes inactive visuals that are activated based on various considerations.

Abstract: A system for simulating maintenance of a reactor core protection system that has at least two or more channels, includes: a simulation signal generation unit for generating a simulation state signal including a normal state or an abnormal state, a communication unit connected to each of the channels of the reactor core protection system to transmit the state signal to the channel, and a control unit for receiving a result signal output from the channel in response to the input simulation state signal and confirming whether the reactor core protection system normally determines a reactor core state by analyzing the result signal.

Abstract: A plant abnormality predict detection system for detectably monitoring an indication of abnormality in an atomic power generation plant is provided with: a data storage unit which stores plant operation data including an instrument parameter measured in the atomic power generation plant; and a monitoring and control unit which, on the basis of the plant operation data, detects an indication of abnormality in the atomic power generation plant, wherein the atomic power generation plant performs a base-load operation so that the instrument parameter has a prescribed target value, and wherein the monitoring and control unit, on the basis of past plant operation data, sets a normal range W that is a range in which the instrument parameter at the current time transitions normally, and detects an indication of abnormality when the instrument parameter at the current time exceeds the normal range W that has been set.

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.

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.

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.

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.

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.

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.

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.

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.

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.

Abstract: An object of the present invention is to assist in describing policies so that errors when describing policies are reduced.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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).

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.

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.

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.

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.

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.