JP7257226B2 - Power plant operation management support device - Google Patents

Description

TECHNICAL FIELD The present invention relates to an operation management support device for a power plant.

A nuclear power plant is a control device that has the function to safely shut down the reactor, protect the reactor core, and start equipment to prevent the spread of radioactive materials to the outside when an abnormality or accident occurs. is installed. In addition, nuclear power plants are provided with operating condition limits, that is, LCO (Limiting Condition of Operation) based on safety regulations that summarize various regulations in nuclear power plants. When investigating the cause of an abnormality or accident in a nuclear power plant and conducting appropriate maintenance work, many related parties such as operators and maintenance personnel of the nuclear power plant may interfere with human error due to LCO. A device for displaying information is known (for example, Patent Document 1).

JP 2012-128674 A

Information on operation and management of nuclear power plants needs to be shared in real time at multiple bases for operation and management of nuclear power plants, and decision-making on countermeasures, etc. must be carried out promptly. However, since the amount of information related to operation management of nuclear power plants is enormous, it has been difficult to share the information in real time among countermeasures offices at multiple bases. In addition, since the information on the operation management of the nuclear power plant is diverse and complicated, it has been difficult to quickly make decisions on countermeasures.

The present invention has been made in view of the above, and an object thereof is to provide an operation management support device for a power plant that enables appropriate sharing of information regarding operation management of a power plant including a nuclear power plant. do.

In order to solve the above-described problems and achieve the object, a power plant operation management support device of the present invention is a power plant operation management support device for supporting the operation management of a power plant. an operating parameter extracting unit for extracting operating parameters of the power plant based on the degree of necessity for management judgment; an information transmission command unit for transmitting information on the operating parameters of the power plant extracted by the operating parameter extracting unit; characterized by comprising

According to this configuration, the information on the operation parameters of the power plant extracted based on the degree of necessity for determining the operation management of the power plant is selected and transmitted, so that the necessary amount of information related to the operation management of the power plant is appropriately transmitted. can be shared. This makes it possible to quickly make accurate decisions regarding countermeasures, etc., based on an appropriate amount of information on operation management of the power plant.

In this configuration, it is preferable that the operating parameter extracting unit extracts a predetermined number of operating parameters of the power plant in descending order of necessity for determination of operation management of the power plant. According to this configuration, it is possible to appropriately limit the information regarding the operation management of the power plant that is shared and taken into consideration in decision making.

In these configurations, it is preferable that the operating parameter extraction unit extracts different operating parameters of the power plant according to operating conditions of the power plant. According to this configuration, it is possible to select and share necessary information according to the operating status of the power plant, and to quickly and accurately make decisions based on the information selected according to the operating status of the power plant. make it possible.

Further, in the configuration in which the operating parameter extracting unit extracts different operating parameters of the power plant according to the operating status of the power plant, the operating parameter extracting unit extracts different operating parameters of the power plant during normal operation of the power plant. Reactor thermal power, reactivity shutdown margin and control rod position information are extracted as parameters, and the minimum shutdown boron concentration and coolable temperature are used as the operating parameters of the power plant for the initial response in the event of an accident of the power plant. and decay heat, and extracting core monitoring information, core decay heat, and SFP decay heat as operating parameters of the power plant at the time of an accident of the power plant. According to this configuration, during normal operation of the power plant, it is possible to share information that is preferable to be shown in order to maintain safety and take it into consideration in decision-making. Information necessary to stop a plant can be shared and taken into consideration in decision-making, and in the event of an accident at a power plant, information necessary to maintain safety in the event of an accident can be shared and taken into consideration in decision-making. be able to.

In these configurations, the information transmission command unit processes the information of the operating parameters of the power plant extracted by the operating parameter extraction unit during normal operation of the power plant and during initial response to an accident of the power plant. Preferably, the information is transmitted using a signal of the system, and in the event of an accident of the power plant, the information of the operating parameter of the power plant extracted by the operating parameter extraction unit is transmitted using the signal of the safety parameter display system. According to this configuration, while the signal of the process control system that can be used fully open during normal operation of the power plant and initial response to an accident is preferably used, part of the signal of the process control system is lost in the event of an accident at the power plant. In response to the unavailability of the power plant, by suitably using the signal of the safety parameter display system that can be used fully open even in the event of an accident of the power plant, information regarding the operation management of the power plant is continuously and stably transmitted. be able to.

These configurations preferably further include a calculation interval setting unit that controls the capacity used for transmission by setting a calculation interval for the information on the operating parameters of the power plant extracted by the operating parameter extracting unit. According to this configuration, especially when a large capacity is used to calculate the operating parameter information for transmission, by limiting the capacity used for calculating the operating parameter information for transmission, the original power plant While limiting the impact on the operation management support function, which is a function of the operation management support device, to the extent that it does not affect accurate decision-making, it is necessary to appropriately share information related to the operation management of the power plant as much as necessary. enable.

In the configuration further including a calculation interval setting unit, the calculation interval setting unit widens the calculation interval of the information on the operating parameters of the power plant extracted by the operating parameter extracting unit, thereby reducing the capacity used for transmission. preferably. According to this configuration, by widening the time interval of the data points of the information on the operating parameters of the power plant, the effect on the operation management support function, which is the original function of the operation management support device for the power plant, can be reduced and the accuracy can be reduced. It is possible to appropriately share information on the operation management of the power plant as much as necessary to the extent that it does not affect the decision making.

FIG. 1 is a schematic configuration diagram of a power plant operation management support device according to an embodiment of the present invention and a power plant in which the power plant operation management support device is used. FIG. 2 is a functional block diagram showing the operation management support device for the power plant in FIG. 3 is a diagram showing the operating parameter information database of FIG. 2. FIG. FIG. 4 is a diagram showing a first display screen, which is an example of a screen displayed on the display unit of the countermeasure room terminal by the power plant operation management support device of FIG. 1 . FIG. 5 is a diagram showing a second display screen, which is an example of a screen displayed on the display unit of the countermeasure room terminal by the power plant operation management support device of FIG. 1 . FIG. 6 is a diagram showing a third display screen, which is an example of a screen displayed on the display unit of the countermeasure room terminal by the power plant operation management support device of FIG. 1 .

DETAILED DESCRIPTION OF THE INVENTION A power plant operation management support device according to an embodiment of the present invention will be described in detail below with reference to the drawings. It should be noted that the following description of the embodiments does not limit the present invention, and can be implemented with appropriate modifications.

[Embodiment]
FIG. 1 is a schematic configuration diagram of a power plant operation management support device 10 according to an embodiment of the present invention and a power plant 22 in which the power plant operation management support device 10 is used. As shown in FIG. 1, the power plant operation management support device 10 supports the operation management of the power plant 22, and also connects the countermeasure room terminals 40 provided in the countermeasure offices at a plurality of bases for the operation management of the power plant 22. and are electrically connected to enable information communication.

First, the plant security system 20 that uses the operation management support function of the power plant operation management support device 10 will be described below. Plant security system 20 includes power plant 22, controller 24, and maintenance tools 26, as shown in FIG. Controllers 24 and maintenance tools 26 are located in a central control room.

The power plant 22 is a nuclear power plant and includes a nuclear reactor 32, a steam generator 34, a pressurizer 36, and an accumulator tank 38, as shown in FIG. The power plant 22 includes a thermometer 32a that measures the temperature inside the nuclear reactor 32, a water level gauge 34a that measures the water level inside the steam generator 34, and a pressure gauge 36a that measures the pressure inside the pressurizer 36. and a measurement system 38a for measuring the boron concentration, the amount of boric acid solution, and the pressure inside the accumulator tank 38 . The power plant 22 also includes various other equipment and instruments. The reactor 32, the thermometer 32a, the steam generator 34, the water level gauge 34a, the pressurizer 36, the pressure gauge 36a, the accumulator tank 38, the measurement system 38a and other various devices and gauges are installed in a typical nuclear power plant. Those used are preferably used. Although the power plant 22 is assumed to be a nuclear power plant in the first embodiment, the present invention is not limited to this and may be a thermal power plant.

The power plant 22 is electrically connected in parallel to four control units 39, which constitute the control device 24 and will be described later, so that information can be communicated. That is, the nuclear reactor 32, the steam generator 34, the pressurizer 36, the accumulator tank 38, and various other devices are electrically connected to the four control units 39 constituting the control device 24 so as to be able to communicate with each other. ing. The nuclear reactor 32, the steam generator 34, the pressurizer 36, the accumulator tank 38, and other various devices included in the power plant 22 are stored in the four control units 39 that make up the control device 24, and various parameters, etc. regarding each device. send information about The nuclear reactor 32 , steam generator 34 , pressurizer 36 , accumulator tank 38 and various other devices included in the power plant 22 are controlled by four control units 39 that make up the controller 24 .

In addition, the thermometer 32a, the water level measuring instrument 34a, the pressure gauge 36a, the measuring system 38a, and other various measuring instruments are electrically connected to the four control units 39 constituting the control device 24 so as to be able to communicate information. there is A thermometer 32a, a water level measuring instrument 34a, a pressure gauge 36a, a measuring system 38a, and other various measuring instruments included in the power plant 22 transmit measurement information from each measuring instrument to four control units 39 that constitute the control device 24. to send.

The control device 24 comprises a plurality of control units, specifically four control units 39 as shown in FIG. The control device 24 may comprise any number of control units without being limited thereto. The controller 24 preferably comprises as many control units as possible. The four control units 39 are device units with the same specifications. Each of the four control units 39 is electrically connected in parallel with the power plant 22 so as to be able to communicate information therewith. The four control units 39 respectively receive the information of each device and control the operation of the power plant 22 based on the received information of each device. The controller 24 processes the same control over the operation of the power plant 22 in parallel with the four control units 39 .

In the plant security system 20, since the power plant 22 is a nuclear power plant, the controller 24 must be quadruple according to LCO (Limiting Condition of Operation). In other words, in the plant safety system 20, it is necessary to maintain a state in which the controller 24 processes the same control regarding the operation of the power plant 22 in parallel with the four control units 39. FIG. In other words, in the plant safety system 20, a state in which the control device 24 processes the same control regarding the operation of the power plant 22 in parallel with three or less control units 39 deviates from the LCO. For this reason, if the power plant 22 is a nuclear power plant, the control device 24 must have four control units 39 . Also, if the power plant 22 is a nuclear power plant, the controller 24 preferably comprises five or more control units 39 .

The LCO is provided based on safety regulations, which are a collection of various rules established for each type of plant. Since the power plant 22 is a nuclear power plant, the plant safety system 20 is provided based on the safety regulations that summarize various regulations in the nuclear power plant, but different LCOs are provided according to the type of plant. The LCO manages restrictions on operating conditions in the form of articles regardless of the type of plant.

The four control units 39 are electrically connected in parallel and in communication with the maintenance tool 26 . The four control units 39 each transmit information on the status of the equipment of the control unit 39 to the maintenance tool 26 . The device status information of the control unit 39 is information indicating whether each part of the control unit 39 is in a normal operating state or in a faulty state.

The four control units 39 send information to the maintenance tool 26, such as various parameters regarding the nuclear reactor 32, the steam generator 34, the pressurizer 36, the accumulator tank 38 and various other equipment included in the power plant 22. . The four control units 39 transmit to the maintenance tool 26 measurement information from thermometers 32 a , water level gauges 34 a , pressure gauges 36 a , measurement systems 38 a and various other measuring devices included in the power plant 22 .

Each of the control units 39 has a circuit for making a control decision for the control device 24, which is exemplified by a CPU (Central Processing Unit) included in a computer. That is, the control units 39 each perform arithmetic processing such as logic arithmetic for controlling the operation of the power plant 22 . The control unit 39 performs arithmetic processing for controlling normal operation within predetermined operating conditions of the power plant 22 when the power plant 22 is operating normally. The predetermined operating conditions of the power plant 22 include the LCO, and are stored in a storage device or the like connected to the control unit 39 .

When an abnormality or accident occurs in the power plant 22, the control unit 39 controls the power plant 22 in response to the abnormality or accident based on the information on the abnormality or accident input to the control device 24. Perform arithmetic processing. For example, the control unit 39 inputs to the control device 24 to maintain and restore the operation of the power plant 22 by a predetermined method when an abnormality or an accident occurs in which the operation can be maintained and restored in the power plant 22. Arithmetic processing for maintaining and restoring the operation of the power plant 22 is performed according to the operation. In addition, the control unit 39 is a pressurized water reactor, and when an abnormality or an accident that makes it impossible to maintain and restore the operation of the power plant 22 requiring a reactor trip occurs, the control device In response to an input indicating that the reactor is to be tripped to 24 , arithmetic processing is performed to trip the power plant 22 .

The control unit 39 preferably has a structure in which a plurality of logic operation circuits are combined. The control unit 39 generates instructions for controlling each section of the power plant 22 by performing calculations set in each logic calculation circuit.

The maintenance tool 26 is an instrumentation panel that collects and displays information necessary for safety protection of the power plant 22 including the nuclear reactor 32, and is sometimes called a nuclear reactor safety protection instrumentation panel. The maintenance tool 26 is electrically connected in parallel to each of the four control units 39 constituting the control device 24 so as to be able to communicate information. The maintenance tool 26 receives from the four control units 39 information on the status of the equipment of each control unit 39 . The maintenance tool 26 has a display and causes the device status information of the respective control unit 39 to be displayed on the display.

The maintenance tool 26 provides, via the four control units 39 that make up the controller 24, various functions related to the reactor 32, the steam generator 34, the pressurizer 36, the accumulator 38 and various other equipment included in the power plant 22. receive information such as parameters. The maintenance tool 26 can monitor the status of the reactor 32, the steam generator 34, the pressurizer 36, the accumulator 38 and various other equipment included in the power plant 22 via the four control units 39 that make up the controller 24. to receive information about Maintenance tool 26 causes a display to show the status of various equipment included in power plant 22 . Specifically, when there is a high possibility that the equipment included in the power plant 22 has failed, the maintenance tool 26 adds the likely failure equipment to an error message or error code regarding the failure. , to appear on the display.

The maintenance tool 26 uses a thermometer 32a, a water level measuring device 34a, a pressure gauge 36a, a measuring system 38a, and other various measuring devices included in the power plant 22 via four control units 39 that constitute the control device 24. Receive measurement information. The maintenance tool 26 controls the temperature gauge 32a, the water level gauge 34a, the pressure gauge 36a, the measurement system 38a, and other various gauges included in the power plant 22 via the four control units 39 that make up the controller 24. Receive status information. Maintenance tool 26 causes a display to show the status of various instruments included in power plant 22 . Specifically, when there is a high possibility that a measuring instrument included in the power plant 22 is out of order, the maintenance tool 26 causes the display to display the equipment that is likely to be out of order.

The maintenance tool 26 divides into three types of input/output alarms, minor failure alarms, and major failure alarms, and displays them on the display. Here, the input/output alarm includes an alarm for a failure related to input/output of information to/from the control unit 39 . Further, the minor failure alarm includes an alarm for failure of one CPU system in the control unit 39 . Further, the serious failure alarm includes an alarm for failure of both CPU systems in the control unit 39 .

Each of the four control units 39 and the maintenance tool 26 is electrically communicable with the arithmetic processing unit 11a of the control unit 11 via the information communication interface 11c of the control unit 11 in the power plant operation management support device 10. and information such as various parameters relating to the reactor 32, the steam generator 34, the pressurizer 36, the accumulator tank 38, and various other equipment included in the power plant 22, as well as Measured information from the thermometer 32a, the water level measuring device 34a, the pressure gauge 36a, the measuring system 38a, and various other measuring devices is input to the arithmetic processing unit 11a of the control unit 11 via the information communication interface 11c.

As shown in FIG. 1, the power plant operation management support device 10 is used in a plant security system 20 that secures a power plant 22, and is connected to other devices including the plant security system 20 so as to be able to communicate information. In the present embodiment, the power plant operation management support device 10 is a computer terminal connected by wire to other equipment including the plant security system 20, but the present invention is not limited to this, and the plant security system 20 can be used as a computer terminal. It may be a portable tablet-like terminal or the like wirelessly connected to another device including the device.

In the present embodiment, the power plant operation management support device 10 is in a form capable of information communication with each part of the plant security system 20 by wire for information communication. In this case, the power plant operation management support device 10 does not adversely affect the devices included in the plant security system 20, particularly measuring instruments that are highly sensitive to radio waves. In addition, since the power plant operation management support device 10 and the plant security system 20 do not perform wireless information communication, information is not leaked wirelessly, and there is no concern about information security. In addition, the power plant operation management support device 10 can transmit various information necessary for the processing of the control unit 11 described later to the input unit 12 described later through the display unit 13 described later, without requesting input to the input unit 12 described later. It can be obtained automatically from system 20 .

The power plant operation management support device 10 is not limited to a form in which information communication with each part of the plant security system 20 is possible by wire. It may be possible to communicate information with each part of the plant security system 20 wirelessly in a wavelength range that does not affect the equipment included in the plant security system 20 . In this case, the power plant operation management support device 10 uses radio waves in a wavelength range that does not affect the equipment included in the plant security system 20, so adverse effects on these equipment are reduced. In addition, since the power plant operation management support device 10 and the plant security system 20 are wirelessly locked, the possibility of information leaking wirelessly is reduced, and concerns about information security are reduced. In addition, the power plant operation management support device 10 automatically receives various information necessary for the processing of the control unit 11 from the plant security system 20 wirelessly without requesting input to the input unit 12 through the display unit 13. can be obtained.

Further, the power plant operation management support device 10 may be in a form in which information communication with each part of the plant security system 20 is impossible, that is, in a form of performing stand-alone processing. In this case, the power plant operation management support device 10 does not adversely affect the devices included in the plant security system 20, particularly measuring instruments that are highly sensitive to radio waves. In addition, since the power plant operation management support device 10 and the plant security system 20 do not perform wireless information communication, information is not leaked wirelessly, and there is no concern about information security. In this case, the power plant operation management support device 10 requests various information necessary for the processing of the control unit 11 to be input to the input unit 12 through the display unit 13. In response to this request, the operator Various information such as information displayed on the display of the maintenance tool 26 can be obtained by inputting it to the input unit 12 .

As shown in FIG. 1, the power plant operation management support device 10 is electrically connected to enable information communication with a countermeasure room terminal 40 provided in a countermeasure room at a base for operation management of the power plant 22. . The power plant operation management support device 10 may be directly connected to the response room terminal 40 by wire or wirelessly so as to be capable of information communication, or may be indirectly connected to be capable of information communication via a desired communication network. may be connected.

The countermeasure room terminal 40 only needs to include a display unit that receives information transmitted from the power plant operation management support device 10 at least and displays the information in the form of characters, images, moving images, etc. In this embodiment, the countermeasure room A suitable example is a large display that can be viewed simultaneously by many people involved in the operation and management of the power plant 22 who are stationed at the power plant 22 . The response room terminal 40 may also be a plurality of personal information processing terminals assigned to each person stationed in the response room. Mobile phones including functional mobile phones (so-called smart phones), tablet terminals, laptop or desktop PCs (Personal Computers), PDA (Personal Digital Assistant) which is a personal digital assistant, and glasses-type and watch-type wearable devices (Wearable Device) and the like are exemplified.

FIG. 2 is a functional block diagram showing the power plant operation management support device 10 of FIG. The power plant operation management support device 10 includes a control unit 11, an input unit 12, and a display unit 13, as shown in FIG. The control unit 11 is electrically connected to the input unit 12 and the display unit 13 so as to be able to communicate information therewith.

The input unit 12 is an interface that receives input of various data from externally connected equipment and an interface that receives input from the user. buttons, mouse and keyboard, etc. are exemplified. Note that the input unit 12 is not limited to this, and may be a touch panel integrated with a display device or the like. The input unit 12 transmits information received as input to the control unit 11 .

The display unit 13 is an interface that displays and outputs various data transmitted from the control unit 11 in the form of characters, images, moving images, etc. In this embodiment, a liquid crystal display device is exemplified. Note that the display unit 13 is not limited to this, and may be a touch panel integrated with an input device or the like.

The control unit 11, as shown in FIG. 2, has an arithmetic processing unit 11a, a storage unit 11b, and an information communication interface 11c. In the present embodiment, a large-capacity computer is exemplified as a suitable example of the control unit 11, but the present invention is not limited to this. As long as it has a large capacity that can withstand, mobile phones including high-performance mobile phones (so-called smart phones), tablet terminals, notebook or desktop PCs, PDA that is a personal digital assistant, and eyeglasses A type or watch type wearable device or the like may be used.

The arithmetic processing unit 11a is a controller, and for example, a CPU (Central Processing Unit), an MPU (Micro Processing Unit) or the like stores data in the storage unit 11b, which is a storage device inside the power plant operation management support device 10. Various programs (corresponding to an example of an operation management support program for a power plant) are executed by using a RAM (Random Access Memory) as a work area. Further, the arithmetic processing unit 11a is, for example, a controller, and is realized by an integrated circuit such as ASIC (Application Specific Integrated Circuit) or FPGA (Field Programmable Gate Array). The arithmetic processing unit 11 a is connected to an information communication interface 11 c that receives various data inputs from the input unit 12 and outputs various data to the display unit 13 .

As shown in FIG. 2, the arithmetic processing unit 11a is electrically connected to the storage unit 11b and the information communication interface 11c so as to be able to communicate information with each other, and performs a control function of controlling each of these components. That is, the arithmetic processing unit 11a fulfills a control function together with the storage unit 11b, and causes the power plant operation management support device 10 according to the embodiment to perform the function.

The arithmetic processing unit 11a has an operating parameter extraction unit 14, an information transmission command unit 15, and a calculation interval setting unit 16, as shown in FIG. Each unit included in the arithmetic processing unit 11a, that is, the operation parameter extracting unit 14, the information transmission command unit 15, and the calculation interval setting unit 16, is operated by the arithmetic processing unit 11a executing the power plant operation management support program. , are the implemented functional units. The specific functions of the operating parameter extraction unit 14, the information transmission command unit 15, and the calculation interval setting unit 16 will be described later.

In addition, the arithmetic processing unit 11a executes various computational processing related to the power plant operation management support processing that is mainly executed by the power plant operation management support device 10 . The arithmetic processing unit 11a acquires measurement data and processing data that can be acquired from the plant security system 20 and the power plant 22 via the information communication interface 11c, and refers to the image creation processing information stored in the storage unit 11b. Then, a display image relating to these measurement data, processing data, etc. is created, and the created display image is transmitted to the display unit 13 or the like via the information communication interface 11c for output.

The arithmetic processing unit 11a also refers to the calculation processing information stored in the storage unit 11b based on the measurement data and processing data that can be acquired from the plant security system 20 and the power plant 22, Calculate each numerical value of each operating parameter related to the content of the LCO, refer to the image creation processing information stored in the storage unit 11b, create a display image for each calculated numerical value, and use the information communication interface The created display images are sent to the display unit 13 or the like via the 11c for output.

The arithmetic processing unit 11a also refers to the determination processing information stored in the storage unit 11b based on each numerical value of each operating parameter related to the content of the calculated LCO of the power plant 22, The operating state is discriminated, the image creation processing information stored in the storage unit 11b is referred to, display images relating to the discriminated operating state are created, and the created display images are displayed via the information communication interface 11c. It is transmitted to the unit 13 or the like to be output.

Here, the operating state of the power plant 22 is roughly divided into two types, normal operation in which the power does not deviate from the LCO, and accident in which the power does not deviate from the LCO. In addition, the operating state of the power plant 22 is roughly divided into two types, when the power plant 22 is in a state of deviation from the LCO at the time of an accident. and an accident time outside the allowable standby exclusion time for LCO deviation, and the power plant 22 is required to be stopped while responding to the LCO deviation. be. In other words, the operating state of the power plant 22 is roughly divided into three types, namely normal operation, initial response to an accident, and accident. The allowable standby exclusion time refers to the time limit allowed until the power plant 22 is restored to a state in which the emergency core cooling system (ECCS) can operate.

The arithmetic processing unit 11a also refers to the handling processing information stored in the storage unit 11b based on the determined operating state, derives the measures to be taken for the power plant 22, and stores the information in the storage unit 11b. By referring to the image creation processing information stored therein, display images relating to the derived correspondence are created, and these created display images are transmitted to the display unit 13 or the like via the information communication interface 11c for output.

The storage unit 11b is implemented by, for example, a semiconductor memory device such as a ROM (Read Only Memory), a RAM (Random Access Memory), a flash memory, or a storage device such as a hard disk or an optical disk. The storage unit 11b stores and saves an operating parameter information database 17, as shown in FIG.

In addition, the storage unit 11b records and stores various kinds of information necessary for computational processing related to power plant operation management support processing mainly executed by the power plant operation management support device 10 . The storage unit 11b records and stores, for example, safety regulation information related to the safety regulation of the power plant 22 as various kinds of information necessary for computational processing related to operation management support processing of the power plant. This safety regulation information recorded and stored in the storage unit 11b includes, among the safety regulations, operating condition restrictions based on the safety regulation that summarizes various regulations in the nuclear power plant, that is, all article numbers related to LCO, Each article associated with each article number, the content of the LCO of the power plant 22, and each operation parameter related to the content of the LCO of the power plant 22 are included.

The storage unit 11b stores various kinds of information necessary for computer processing related to operation management support processing of the power plant. Record and store information. The operating state determination information recorded and stored in the storage unit 11b is related to the contents of the LCO of the power plant 22 based on the measurement data and processing data that can be acquired from the plant safety system 20 and the power plant 22. Calculation processing information necessary for calculating each numerical value of each operating parameter, each numerical value such as obtainable measurement data and processing data, and each operating parameter related to the content of the calculated LCO of the power plant 22 Judgment processing information used for computer processing based on logic such as permissible upper limit value, permissible lower limit value and inequality necessary for judging the operating state based on each numerical value, and power plant 22 based on the judged operating state and handling processing information including comparison information of judgment contents and handling contents necessary for deriving the handling to be performed.

Here, the measurement data, processing data, and the like that can be acquired from the plant security system 20 and the power plant 22 include, as information on each operating parameter of the power plant 22, information that the control device 24 receives input from the power plant 22, control information on the controlled object to be controlled in the power plant 22 by the device 24 performing arithmetic processing and transmitting it to the power plant 22; It is included.

In addition, the storage unit 11b stores information on the periodical check time related to the time interval for automatically recording the state of the power plant 22. FIG. The storage unit 11b stores image elements (character information of various fonts, basic image information such as icons, graph creation processing information, layout information, etc.) used for images created by the arithmetic processing unit 11a and displayed on the display unit 13. , etc.) is stored.

The storage unit 11b automatically stores and saves various kinds of information acquired or generated by processing by the arithmetic processing unit 11a. The storage unit 11b also automatically stores various information acquired or generated by processing by each unit included in the arithmetic processing unit 11a, that is, the operation parameter extraction unit 14, the information transmission command unit 15, and the calculation interval setting unit 16. Remember and save.

The information communication interface 11c connects the arithmetic processing unit 11a, the input unit 12, the display unit 13, the plant security system 20, the power plant 22, and the countermeasure room terminal 40 by wire or wirelessly so that information can be communicated with each other. The information communication interface 11c may connect the arithmetic processing unit 11a and the response room terminal 40 via a desired communication network so as to enable information communication.

As described above, the operation management support device 10 for a power plant according to the embodiment has various display images created and displayed by the arithmetic processing unit 11a in consideration of various information stored in the storage unit 11b. Through the display, operation management of the power plant 22 is supported for many concerned parties such as operators and maintenance personnel of the power plant 22 .

The information communication interface 11c receives measurement data, processing data, and the like that can be acquired from the plant security system 20 and the power plant 22 from the plant security system 20 and the power plant 22, respectively, and transmits the data to the arithmetic processing unit 11a.

The information communication interface 11c receives various data input by the input unit 12 from the input unit 12 and transmits the data to the arithmetic processing unit 11a. The information communication interface 11 c receives various data generated by the arithmetic processing unit 11 a from the arithmetic processing unit 11 a and transmits the data to the display unit 13 and the response room terminal 40 .

FIG. 3 is a diagram showing the operating parameter information database 17 of FIG. As shown in FIG. 3, the operating parameter information database 17 includes an operating parameter 17a, and respective necessity levels 17b and 17c for three types of operating states of the power plant 22, i.e., during normal operation, during initial response to an accident, and during an accident. , 17d are registered in a one-to-one correspondence. Here, the degree of necessity is the degree of necessity for determining the operation management of the power plant 22, and is determined based on the number of times of reference in the operation management support of the power plant 22, the degree of relevance to the LCO, and the like. is a parameter. The degree of necessity may be calculated and registered by the arithmetic processing unit 11a based on the number of times of reference and the degree of LCO relevance, or may be manually input from the input unit 12 by the operator and registered. In the present embodiment, the degree of necessity is represented by integers in 10 stages from 1 to 10, and the higher the numerical value, the higher the necessity. can be changed as appropriate.

Reactor Thermal Power (RTP), which is one of the operating parameters 17a exemplified in the operating parameter information database 17 shown in FIG. , the energy converted into electricity, and the amount of heat imparted to the thermal wastewater. For this reason, since the reactor thermal output is referred to many times during normal operation, the necessity level 17b is as high as 10, and the necessity levels 17c and 17d are both 1 because they are rarely referred to during the initial response to an accident and during an accident. and is registered as low.

The reactivity shutdown margin (SDM), which is one of the operating parameters 17a exemplified in the operating parameter information database 17 shown in FIG. This is the reactivity of the reactor 32 and is a parameter used as an important measure of the shutdown capability of the reactor 32 . The reactivity termination margin is a parameter indicating that the higher the reactivity termination margin, the higher the safety. For this reason, the reactivity stop margin is frequently referred to as an index of safety during normal operation, so the degree of necessity 17b is as high as 9. 17d are all registered as low as 1.

Control rod position information (Control Rod Position Information), which is one of the operating parameters 17a exemplified in the operating parameter information database 17 shown in FIG. This is a parameter used to calculate the stop margin. For this reason, the control rod position information is frequently referred to as an index of safety during normal operation, so the degree of necessity 17b is as high as 8. 17d are all registered as low as 1.

FQ, which is one of the operating parameters 17a exemplified in the operating parameter information database 17 shown in FIG. A parameter representing a safety factor that compensates for the hot channel, which has the highest temperature, taking into account the spatial distribution of the core power and the non-uniform flow of the reactor coolant in the core. be. For this reason, FQ is frequently referred to as an index of safety during normal operation, so the necessity level 17b is relatively high at 6, and the necessity levels 17c and 17d are rarely referred to during the initial response to an accident and at the time of an accident. are all registered as low as 1.

FΔHN, which is one of the operating parameters 17a exemplified in the operating parameter information database 17 shown in FIG. As with the hot water channel coefficient, considering the spatial distribution of the core power of the reactor 32 and the non-uniform flow of the reactor coolant in the core, the fuel coolant channel with the highest temperature (hot channel ) is a parameter that represents a safety factor that corrects for For this reason, FΔHN is frequently referred to as an indicator of the degree of safety during normal operation, so the degree of necessity 17b is relatively high at 6, and the degrees of necessity 17c and 17d are scarcely referenced during the initial response to an accident and at the time of an accident. are all registered as low as 1.

DNBR, which is one of the operating parameters 17a exemplified in the operating parameter information database 17 shown in FIG. 3, is the Departure from Nucleate Boiling Ratio. It is a parameter expressed as a ratio value related to the heat flux at which a sudden transition to film boiling occurs when the surface is covered with a vapor film, ie the critical heat flux (Departure from Nucleate Boiling). For this reason, the DNBR is frequently referred to as an index of safety during normal driving, and the necessity level 17b is relatively high at 6; are all registered as low as 1.

Minimum Boron Concentration for Shutdown, which is one of the operating parameters 17a exemplified in the operating parameter information database 17 shown in FIG. It is the concentration, and is a parameter referred to when injecting a sodium pentaborate solution containing ¹⁰ B to stop the nuclear reaction in the nuclear reactor 32 during the initial response to an accident of the power plant 22. For this reason, the minimum shutdown boron concentration is an important parameter that may be referred to during the initial response to an accident, so the degree of necessity 17c is as high as 10, and the degree of necessity 17b is hardly referenced during normal operation and during an accident. , 17d are registered as low as 2 and 4, respectively.

Cooling Limit, which is one of the operating parameters 17a exemplified in the operating parameter information database 17 shown in FIG. This is the temperature, and is a parameter that is particularly referred to during the initial response to an accident at the power plant 22 and may also be referred to at the time of an accident at the power plant 22 . For this reason, the coolable temperature is an important parameter that may be referred to during the initial response in the event of an accident. The necessity level 17b is registered as low as 2 because it is relatively high and is rarely referred to during normal operation.

Core monitoring information, which is one of the operating parameters 17a exemplified in the operating parameter information database 17 shown in FIG. , the concentration of boron (CB), and the density ρ of radioactive materials accumulated in the core. For this reason, the core monitoring information is an important parameter that may be referred to in the event of an accident when the possibility of monitoring the reactor 32 increases. The degree of necessity 17c is registered as 6, which is relatively high, because there is a possibility, and the degree of necessity 17b, which is 1, is registered as low as it is rarely referred to during normal operation.

Core decay heat, which is one of the operating parameters 17a exemplified in the operating parameter information database 17 shown in FIG. This parameter represents the amount of heat generated by the decay of radioactive materials such as fuel in the core of No. 32. Immediately after the reactor 32 stops, the decay heat emitted by radioactive nuclides among the products generated by nuclear fission may reach about 5 to 6% of the reactor thermal output of the reactor 32, so the pressure accumulator tank If an accident occurs in the nuclear reactor 32 that stops the cooling function of the 38, etc., the temperature of the core of the nuclear reactor 32 rises unless the decay heat is removed by activating the decay heat removal system. A situation where the fuel melts may occur. For this reason, core decay heat is an important parameter that may be referred to during the initial response to an accident, when there is a high possibility that removal of decay heat is required, and in the event of an accident. , the necessity level 17b is registered as low as 1 because it is hardly referred to during normal operation.

SFP decay heat (Decay Heat from Spent Fuel Pools), which is one of the operating parameters 17a exemplified in the operating parameter information database 17 shown in FIG. It is the decay heat accumulated in the spent fuel pool, and is a parameter that expresses the amount of heat generated by the decay of radioactive materials such as fuel in the spent fuel pool. For this reason, the SFP decay heat is a parameter that may be referred to in an accident when there is a higher possibility that decay heat removal is required, so the necessity level 17d is as high as 7, and the possibility that decay heat removal is required is high. The necessity level 17c is registered as 6, which is relatively high, because there is a relatively high possibility that it will be referred to during the initial response in the event of an accident.

Core reactivity, which is one of the operating parameters 17a exemplified in the operating parameter information database 17 shown in FIG. For example, it is represented by a value obtained by dividing the neutron excess multiplication factor by the neutron effective multiplication factor, the critical state of the reactor 32 is represented by 0, the supercritical state of the reactor 32 is represented by a positive value, The subcritical state of the reactor 32 is a parameter represented by a negative value. Here, the critical state is a state in which the neutrons generated by nuclear fission in the nuclear reactor 32 are continuously balanced between the neutrons that contribute to the next nuclear fission and the neutrons that escape from the system. . For this reason, the reactivity of the core is an important parameter that may be referred to in the event of an accident in which the possibility of the reactor 32 being in a critical or supercritical state increases. The necessity level 17c is registered as 5, which is neither high nor low, because there is a possibility that it may be referred to during the initial response at the time of an accident.

Note that the operating parameter information database 17 shown in FIG. 3 exemplifies the above-described operating parameters 17a, but preferably further includes other operating parameters 17a that are not illustrated. When other operating parameters 17a are further included, these operating parameters 17a are registered in one-to-one correspondence with the degrees of necessity 17b, 17c, and 17d, similarly to the above-described operating parameters 17a. Moreover, the respective necessity levels 17b, 17c, and 17d are arbitrarily determined, and the values shown in this specification and FIG. 3 are examples.

The operating parameter extraction unit 14 of the arithmetic processing unit 11a extracts the operating parameters of the power plant 22 based on the degree of necessity for determining the operation management of the power plant 22 . Specifically, the operating parameter extraction unit 14 preferably extracts a predetermined number of operating parameters of the power plants 22 in descending order of necessity for determining the operation management of the power plants 22 . Moreover, the operating parameter extraction unit 14 preferably extracts operating parameters of different power plants 22 according to the operating conditions of the power plants 22 .

More specifically, the operating parameter extracting unit 14 refers to the operating parameter information database 17 stored and saved in the storage unit 11b, and extracts three types of operating states of the power plant 22, namely normal operation and initial operation at the time of an accident. About 3 or more and 6 or less operation parameters 17a of power plants 22 are extracted in descending order of necessity 17b, 17c, and 17d for each of response time and accident time.

For example, when the operating parameter extraction unit 14 refers to the operating parameter information database 17 shown in FIG. and extract control rod position information. In addition, for example, the operating parameter extraction unit 14, for the initial response to an accident of the power plant 22, sets the minimum shutdown boron concentration, the coolable temperature, and the decay heat (=core decay heat) as the operating parameters 17a of the power plant 22. to extract Further, the operating parameter extracting unit 14, for example, at the time of an accident of the power plant 22, as the operating parameters 17a of the power plant 22, the reactivity of the core, radioactive substances accumulated in the core and decay heat (= core decay heat and SFP decay heat). Note that the operating parameter extracting unit 14 has a relatively reduced load, such as capacity, on the power plant operation management support device 10 during normal operation of the power plant 22 compared to initial response to an accident and during an accident. Therefore, the number of extracted operating parameters 17a may be increased. In this case, FQ, FΔHN and DNBR are additionally extracted in addition to the reactor thermal power, reactivity shutdown margin and control rod position information. may

The information transmission command unit 15 included in the arithmetic processing unit 11a transmits information on the operation parameters 17a of the power plant 22 extracted by the operation parameter extraction unit 14. FIG. Specifically, the information transmission command unit 15 first refers to the image creation processing information stored in the storage unit 11b based on the information of the operation parameters 17a of the power plant 22 extracted by the operation parameter extraction unit 14. Then, a display image relating to the operating parameters 17a of these power plants 22 is created. The information transmission command unit 15 then transmits these created display images (for example, the first display screen 53, the second display screen 54 and the third display screen shown in FIGS. 4, 5 and 6) via the information communication interface 11c. The display screen 55) is transmitted to the countermeasure room terminal 40 and displayed on the display unit of the countermeasure room terminal 40. FIG. Details of the first display screen 53, the second display screen 54, and the third display screen 55 shown in FIGS. 4, 5, and 6 will be described later.

Here, the information communication system used around the power plant operation management support device 10, including the information communication path from the power plant operation management support device 10 to the countermeasure room terminal 40, is used for information communication, the process control system ( Process Control Computer System (PCCS) signals (hereinafter referred to as PCCS signals) and Safety Parameter Display System (SPDS) signals (hereinafter referred to as SPDS signals) are preferably used together.

The process control system is a computer system for control and is a system composed of computers and peripherals used to control and monitor the operating parameters 17 a of the power plant 22 . PCCS signals are signals used for information communication in such process control systems. The safety parameter display system is a kind of permanent severe accident mitigation equipment of the power plant 22 and a backup transmission line system. The safety parameter display system is composed of, for example, a predetermined data transmission device, a wireless communication antenna, and the like. The SPDS signal is the signal used for information communication in such safety parameter display systems. The SPDS signal can be advantageously used when the PCCS signal is interrupted, such as during an accident at the power plant 22 .

When such an information communication system is used around the power plant operation management support device 10, the information transmission command unit 15, during normal operation of the power plant 22 and during initial response to an accident in the power plant 22, The information of the operating parameters 17a of the power plant 22 extracted by the operating parameter extracting unit 14 is transmitted using a PCCS signal, and in the event of an accident of the power plant 22, the operating parameters 17a of the power plant 22 extracted by the operating parameter extracting unit 14 are transmitted. Information is preferably transmitted using SPDS signals.

The calculation interval setting unit 16 included in the arithmetic processing unit 11 a sets calculation intervals for the information on the operation parameters 17 a of the power plant 22 extracted by the operation parameter extraction unit 14 . For example, the calculation interval setting unit 16 sets a time interval for calculating the operation parameter 17a, which is measured and calculated at regular time intervals by the arithmetic processing unit 11a and displayed as a graph of changes over time. set. Further, the calculation interval setting unit 16 sets the spatial interval for calculating the operating parameter 17a for the operating parameter 17a that is to be measured and calculated for each fixed space by the arithmetic processing unit 11a and displayed as a graph of the spatial distribution. set.

When calculating the operating parameters 17a, the arithmetic processing unit 11a uses the capacity of the RAM, which is the work area of the CPU, MPU, etc., depending on the calculation method of the operating parameters 17a. For this reason, the calculation interval setting unit 16 controls the calculation interval of the information of the operation parameter 17a, that is, by controlling the time interval or the space interval, etc. You can control the volume that is applied. In addition, the calculation interval setting unit 16 widens the calculation interval of the information of the operation parameter 17a, that is, widens the time interval or the space interval, so that the capacity used for the calculation of the operation parameter 17a by the arithmetic processing unit 11a can be reduced. Note that the capacity used for calculation of the operating parameters 17a by the arithmetic processing unit 11a is part of the capacity used for transmitting information on the operating parameters 17a.

The information communication path from the operation management support device 10 of the power plant to the response room terminal 40 uses a capacity based on the capacity of the information to be sent when the information of the operation parameter 17a is sent. For this reason, the calculation interval setting unit 16 controls the calculation interval of the information of the operation parameter 17a, that is, controls the time interval or the space interval, etc., so that the capacity of the information of the operation parameter 17a to be transmitted is reduced. can be controlled to control the capacity used in the information communication path from the power plant operation management support device 10 to the response room terminal 40 . Further, the calculation interval setting unit 16 widens the calculation interval of the information of the operating parameter 17a, that is, widens the time interval or the space interval, thereby reducing the volume of the information of the operating parameter 17a to be transmitted. Thus, the capacity used in the information communication path from the power plant operation management support device 10 to the response room terminal 40 can be reduced. The capacity used in the information communication path from the power plant operation management support device 10 to the response room terminal 40 is a part of the capacity used for transmitting the information of the operation parameter 17a.

For example, the calculation interval setting unit 16 changes the setting of the time interval for calculating the information of the operation parameter 17a to 12 hours, so that when transmitting the capacity used for calculating the operation parameter 17a and the information of the operation parameter 17a, information communication is performed. Advantageously, the capacity used in the path can be reduced.

FIG. 4 is a diagram showing a first display screen 53, which is an example of a screen displayed on the display unit of the response room terminal 40 by the power plant operation management support device 10 of FIG. FIG. 5 is a diagram showing a second display screen 54, which is an example of a screen displayed on the display unit of the response room terminal 40 by the power plant operation management support device 10 of FIG. FIG. 6 is a diagram showing a third display screen 55, which is an example of a screen displayed on the display unit of the response room terminal 40 by the power plant operation management support device 10 of FIG. An example of a screen displayed on the display unit of the response room terminal 40 by the power plant operation management support device 10 will be described below with reference to FIGS. 4, 5, and 6. FIG.

The first display screen 53, the second display screen 54 and the third display screen 55 are all embedded in the display screen 50 having a frame structure as shown in FIGS. are displayed so that they can be switched with each other. Note that the display form of the screen is not limited to this, and can be changed as appropriate. Also, the scales and values shown in FIGS. 4, 5 and 6 are exemplary.

As shown in FIGS. 4, 5 and 6, the display screen 50 having a frame structure includes a header screen portion 51 provided in the upper portion and a portion excluding the header screen portion 51 in the lower portion of the header screen portion 51. and a main screen portion 52 provided.

The header screen portion 51 is common to any one of the first display screen 53, the second display screen 54 and the third display screen 55, and as shown in FIGS. The screen portion 51 has, in order from the left side, a power plant name display 51a, a monitoring state display 51b, and a time display 51c. The power plant name display 51 a displays the name of the power plant 22 . The monitoring state display 51b displays whether or not the power plant 22 with the name displayed in the power plant name display 51a is being monitored. Display medium. The monitoring status display 51b displays, for example, "non-monitoring" when it is not monitoring. The time display 51c displays the current time.

The main screen portion 52 is a portion in which the first display screen 53, the second display screen 54 and the third display screen 55 are respectively embedded. A first tab 52a for displaying a first display screen 53 by accepting a selection, a second tab 52b for displaying a second display screen 54 by accepting a selection, and a third display screen 55 by accepting a selection. and a third tab 52c that allows Therefore, even when any one of the first display screen 53, the second display screen 54, and the third display screen 55 is displayed embedded in the main screen portion 52, the main screen portion can be displayed by selecting the first tab 52a. The screen embedded in 52 can be switched to the first display screen 53, and by selecting the second tab 52b, the screen embedded in the main screen portion 52 can be switched to the second display screen 54, and the third tab 52c can be switched. By selecting , the screen embedded in the main screen portion 52 can be switched to the third display screen 55 .

The first tab 52a displays a character string of the main LCO, which is an item to be checked during normal operation of the power plant 22. By selecting this, the operation parameter extraction unit 14 is displayed during normal operation of the power plant 22. The screen is switched to the first display screen 53 that displays the extracted operating parameters 17 a of the power plant 22 .

As shown in FIG. 4 , the first display screen 53 displays the reactor thermal output, reactivity shutdown margin, control The rod position information, FQ, FΔHN and DNBR are arranged and displayed in respective display portions 53a, 53b, 53c, 53d, 53e and 53f. Of these operating parameters 17a of the power plant 22, the first display screen 53 displays the reactor thermal output, the reactivity shutdown margin, and the control rod position information, which are highly necessary for determining the operation management of the power plant 22, on the screen. They are arranged and displayed in respective display portions 53a, 53b, and 53c in the upper row.

The first display screen 53 displays, among the operating parameters 17a of the power plant 22 extracted by the operating parameter extraction unit 14 for the normal operation of the power plant 22, the reactor thermal output, reactivity shutdown margin, FQ, FΔHN, and DNBR, It is displayed as a graph of time change obtained by measurement, calculation, etc. at regular time intervals by the arithmetic processing unit 11a. The first display screen 53 displays the control rod position information among the operating parameters 17a of the power plant 22 as a graph of the spatial distribution obtained by measuring and calculating for each control rod. Of the operating parameters 17a of the power plant 22, the first display screen 53 superimposes the reactivity shutdown margin, FQ, FΔHN, and DNBR on the time change graph and displays the LCO specified values of these operating parameters 17a. In addition, it is displayed that the LCO judgment is in a pass state for any of the operating parameters 17a.

In the first display screen 53, the graph of the time change of the reactor thermal output among the operating parameters 17a of the power plant 22 extracted by the operating parameter extraction unit 14 during normal operation of the power plant 22 is interrupted. Further, on the first display screen 53, among these operating parameters 17a, the graphs of the time change of the reactivity stoppage margin, FQ, FΔHN, and DNBR are interrupted in the middle. The broken graph shows monitoring values from the past to the present. Points plotted discretely are predicted values from the present, and this time interval is changed based on the change in the setting of the calculation interval of the information of these operating parameters 17a by the calculation interval setting unit 16. be.

The second tab 52b displays a character string of a parameter for stopping the plant, which is an item to be checked during the initial response to an accident of the power plant 22. By selecting this, the initial response to an accident of the power plant 22 is displayed. The second display screen 54 displays the operating parameters 17a of the power plant 22 extracted by the operating parameter extracting unit 14 about time.

As shown in FIG. 5 , the second display screen 54 displays the minimum stop boron concentration, the coolable The temperature, core decay heat, and core reactivity are arranged and displayed at respective display portions 54a, 54b, 54c, and 54d. Further, the second display screen 54 displays the core decay heat numerically in the display portion 54c as well as graphically in the display portion 54e. The second display screen 54 displays the minimum shutdown boron concentration, coolable temperature, and core collapse so that many people stationed in the countermeasures office and engaged in operation management of the power plant 22 can clearly judge the initial response. Regarding heat, it is divided into cases for each situation and displayed numerically. The second display screen 54 is displayed so that many persons stationed in the countermeasures office and engaged in the operation management of the power plant 22 can easily understand the time change of the state of the nuclear reactor 32 of the power plant 22 at a glance. , the reactivity of the core is displayed graphically, and information on criticality is superimposed on this graph.

The third tab 52c displays a character string for monitoring at the time of an accident, which is an item to be checked at the time of an accident at the power plant 22. By selecting this, the operation parameter extracting unit 14 extracts at the time of an accident at the power plant 22. The screen is switched to the third display screen 55 that displays the operating parameters 17a of the generated power plant 22 .

As shown in FIG. 5, the third display screen 55 displays the core information, core decay heat, and SFP decay heat, which are the operating parameters 17a of the power plant 22 extracted by the operating parameter extracting unit 14 at the time of the accident of the power plant 22. They are arranged and displayed in each display portion 55a, 55b, 55c. Since the third display screen 55 is a screen after responding to an accident, core monitoring information is displayed in the display portion 55a, but this information is highly necessary before responding to an accident. , the same information as the reactivity of the core displayed in the display portion 54d of the second display screen 54 is preferably displayed. The core monitoring information displayed on the display portion 55a includes core pressure [unit; MPa], core average temperature [unit; °C], rod cluster control (RCC) [unit; Step], boron concentration (CB) [unit ppm], and the density ρ of radioactive materials accumulated in the core [unit: ppm]. Graphs of information on the core decay heat and the SFP decay heat shown in the display portions 55b and 55c, respectively, show that many people stationed in the countermeasures office and engaged in the operation management of the power plant 22 are aware of the safety of the core. The safety analysis conditions are superimposed so that it is easy to make a clear judgment.

As described above, the power plant operation management support device 10 selects and transmits information on the operation parameters 17a of the power plant 22 extracted based on the degree of necessity for determining the operation management of the power plant 22. 22 operation management information can be appropriately shared as much as necessary. As a result, the power plant operation management support device 10 can quickly make accurate decisions regarding countermeasures based on an appropriate amount of information on the operation management of the power plant 22 .

In the power plant operation management support device 10, the operation parameter extraction unit 14 extracts a predetermined number of the operation parameters 17a of the power plants 22 in descending order of necessity 17b, 17c, and 17d for determining the operation management of the power plants 22. Extract. Therefore, the power plant operation management support device 10 can appropriately limit the information regarding the operation management of the power plant 22 that is shared and taken into consideration in decision making.

In addition, in the power plant operation management support device 10 , the operating parameter extracting unit 14 extracts the operating parameters 17 a of different power plants 22 according to the operating conditions of the power plants 22 . Therefore, the power plant operation management support device 10 can select and share necessary information according to the operating status of the power plant 22, and based on the information selected according to the operating status of the power plant 22, Enables quick and accurate decision making.

In the power plant operation management support device 10, the operation parameter extraction unit 14 uses the reactor thermal output, the reactivity shutdown margin, and the control rod position as the operation parameters 17a of the power plant 22 during normal operation of the power plant 22. Information is extracted, and the minimum shutdown boron concentration, coolable temperature, and decay heat are extracted as the operating parameters 17a of the power plant 22 for the initial response at the time of the accident of the power plant 22. Core monitoring information, core decay heat, and SFP decay heat are extracted as the operating parameters 17a of the power plant 22 . Therefore, the operation management support device 10 for the power plant can share information that is preferably shown to maintain safety during normal operation of the power plant 22 and take it into consideration for decision-making, During the initial response, the information necessary to stop the power plant 22 during the initial response can be shared and taken into consideration in decision-making, and in the event of an accident at the power plant 22, it is necessary to show it in order to maintain safety in the event of an accident. information can be shared and taken into consideration in decision-making.

In the power plant operation management support device 10, the information transmission command unit 15 controls the power plant 22 extracted by the operation parameter extraction unit 14 during normal operation of the power plant 22 and during initial response to an accident of the power plant 22. The information of the operating parameter 17a is transmitted using the signal of the process control system, and in the event of an accident of the power plant 22, the information of the operating parameter 17a of the power plant 22 extracted by the operating parameter extraction unit 14 is transmitted to the signal of the safety parameter display system. Send using For this reason, the power plant operation management support device 10 preferably uses the signal of the process control system that can be used fully open during normal operation of the power plant 22 and during initial response to an accident, and at the time of an accident of the power plant 22 Operation management of the power plant 22 is achieved by suitably using the signal of the safety parameter display system that can be used fully open even in the event of an accident of the power plant 22 in response to the unavailability of some of the signals of the process control system. information can be continuously and stably transmitted.

In addition, the power plant operation management support device 10 sets a calculation interval for information on the operation parameter 17a of the power plant 22 extracted by the operation parameter extraction unit 14, thereby setting a calculation interval for controlling the capacity used for transmission. It further has a portion 16 . For this reason, the power plant operation management support device 10 limits the capacity used to calculate the information of the operating parameters 17a for transmission, particularly when a large capacity is used to calculate the information of the operating parameters 17a for transmission. By doing so, while limiting the influence on the operation management support function, which is the original function of the operation management support device 10 for the power plant, information on the operation management of the power plant 22 is obtained to the extent that accurate decision-making is not affected. can be appropriately shared as needed.

In the power plant operation management support device 10, the calculation interval setting unit 16 widens the calculation interval of the information on the operation parameter 17a of the power plant 22 extracted by the operation parameter extraction unit 14, so that the capacity used for transmission to reduce For this reason, the operation management support device 10 for the power plant widens the time interval of the data points of the information of the operation parameter 17a of the power plant 22, so that the operation management support device 10, which is the original function of the operation management support device 10 for the power plant. It is possible to appropriately share information on the operation management of the power plant 22 as much as necessary while reducing the influence on functions to the extent that accurate decision-making is not affected.

REFERENCE SIGNS LIST 10 power plant operation management support device 11 control unit 11a arithmetic processing unit 11b storage unit 11c information communication interface 12 input unit 13 display unit 14 operation parameter extraction unit 15 information transmission command unit 16 calculation interval setting unit 17 operation parameter information database 17a operation Parameter 17b, 17c, 17d Necessity 20 Plant safety system 22 Power plant 24 Control device 26 Maintenance tool 32 Reactor 32a Thermometer 34 Steam generator 34a Water level measuring instrument 36 Pressurizer 36a Pressure gauge 38 Accumulator tank 38a Measurement system 39 Control unit 40 Response room terminal 50 Display screen 51 Header screen 51a Power plant name display 51b Monitoring status display 51c Time display 52 Main screen 52a First tab 52b Second tab 52c Third tab 53 First display screen 53a, 53b, 53c, 53d, 53e, 53f, 54a, 54b, 54c, 54d, 54e, 55a, 55b, 55c display part 54 second display screen 55 third display screen

Claims (6)

A power plant operation management support device for supporting operation management of a power plant,
an operating parameter extracting unit that extracts operating parameters of the power plant based on the degree of necessity for determining operation management of the power plant;
an information transmission command unit that transmits information on the operating parameters of the power plant extracted by the operating parameter extracting unit;
with
The operating parameter extracting unit performs different power generation for each of three types of operating conditions of the power plant: during normal operation of the power plant, during initial response to an accident of the power plant, and during an accident of the power plant. An operation management support device for a power plant, characterized by extracting plant operation parameters . 2. The operation management of the power plant according to claim 1, wherein the operation parameter extracting unit extracts a predetermined number of operation parameters of the power plant in descending order of necessity for determining the operation management of the power plant. support equipment. The operating parameter extraction unit is
During normal operation of the power plant, extracting reactor thermal power, reactivity shutdown margin and control rod position information as operating parameters of the power plant,
Extract the minimum shutdown boron concentration, coolable temperature and decay heat as the operating parameters of the power plant for the initial response in the event of an accident of the power plant,
3. The operation management of the power plant according to claim 1, wherein core monitoring information, core decay heat and SFP decay heat are extracted as the operating parameters of the power plant at the time of an accident of the power plant. support equipment. The information transmission command unit uses signals of the process control system for the information on the operating parameters of the power plant extracted by the operating parameter extracting unit during normal operation of the power plant and during initial response to an accident in the power plant. and, in the event of an accident of the power plant, the information of the operating parameters of the power plant extracted by the operating parameter extraction unit is transmitted using a signal of a safety parameter display system. The power plant operation management support device according to claim 3 . 2. A calculation interval setting unit for controlling a capacity used for transmission by setting a calculation interval for the information of the operation parameters of the power plant extracted by the operation parameter extraction unit. The power plant operation management support device according to claim 4 . 6. The method according to claim 5 , wherein the calculation interval setting unit reduces the capacity used for transmission by widening a calculation interval of the information on the operating parameters of the power plant extracted by the operating parameter extracting unit. An operation management support device for the power plant described.

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