JP2020169964A - Device for supporting management of operation of power-generating plant - Google Patents

Abstract

To provide a device for supporting management of operation of a power-generating plant which allows a proper share of information on management of operation of a power-generating plant including a nuclear power plant.SOLUTION: A device 10 for supporting management of operation of a power-generating plant is for supporting management of operation of a power-generating plant 22, and includes an operation parameter extraction unit 14 and an information sending instruction unit 15. The operation parameter extraction unit 14 extracts an operation parameter of the power-generating plant 22 on the basis of the necessity of determination about managing the operation of the power-generating plant 22. The information sending instruction unit 15 sends information of the operation parameter of the power-generating plant 22 extracted by the operation parameter extraction unit 14.SELECTED DRAWING: Figure 2

Description

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

A nuclear plant is a control device that has the function of safely shutting down a nuclear reactor, protecting the core, and starting equipment to prevent the diffusion of radioactive materials to the outside in the event of an abnormality or accident. Is installed. In addition, nuclear power plants are provided with LCO (Limiting Condition of Operation), which is the limitation of operating conditions based on the safety regulations that summarize various rules in nuclear power plants. Regarding LCO, which may cause conflicts due to human error by a large number of stakeholders such as nuclear plant operators and maintenance officers when investigating the cause of an abnormality or accident in a nuclear plant and performing appropriate maintenance work. A device for displaying information is known (for example, Patent Document 1).

Japanese Unexamined Patent Publication No. 2012-128674

Information on the operation management of nuclear power plants needs to be shared in real time at multiple countermeasure centers for operation management of nuclear power plants, and decision-making on countermeasures, etc. needs to be executed promptly. However, since the information on the operation management of nuclear power plants has a huge capacity, it is difficult to share it in real time at countermeasure stations at multiple bases. In addition, since the information on the operation management of nuclear power plants is diverse and complicated, it was difficult to promptly make decisions on countermeasures.

The present invention has been made in view of the above, and an object of the present invention is to provide a power plant operation management support device capable of appropriately sharing information on operation management of a power plant including a nuclear power plant. To do.

In order to solve the above-mentioned problems and achieve the object, the power plant operation management support device of the present invention is a power plant operation management support device that supports the operation management of the power plant, and is an operation of the power plant. An operation parameter extraction unit that extracts the operation parameters of the power plant based on the necessity of management judgment, an information transmission command unit that transmits information on the operation parameters of the power plant extracted by the operation parameter extraction unit, It is characterized by having.

According to this configuration, the information on the operation parameters of the power plant extracted based on the necessity of judgment of the operation management of the power plant is selected and transmitted, so that the information on the operation management of the power plant is appropriately obtained as much as necessary. Can be shared. This makes it possible to promptly make accurate decisions regarding countermeasures, etc., based on information on the operation management of an appropriate amount of power plants.

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

In these configurations, it is preferable that the operation parameter extraction unit extracts different operation parameters of the power plant according to the operation status of the power plant. According to this configuration, necessary information can be selected and shared according to the operating status of the power plant, and accurate decision-making can be promptly executed based on the information selected according to the operating status of the power plant. Make it possible.

Further, in a configuration in which the operation parameter extraction unit extracts different operation parameters of the power plant according to the operation status of the power plant, the operation parameter extraction unit operates the power plant during normal operation of the power plant. Reactor heat output, reaction rate stop margin and control rod position information are extracted as parameters, and for the initial response in the event of an accident at the power plant, the minimum stop boron concentration and coolable temperature are the operating parameters of the power plant. And decay heat are extracted, and it is more preferable to extract core monitoring information, core decay heat and SFP decay heat as operating parameters of the power plant in the event of an accident at the power plant. According to this configuration, information that is preferable to be shown in order to maintain safety during normal operation of the power plant can be shared and used for decision making, and power is generated at the time of initial response in the event of an accident at the power plant. Information necessary to shut down the plant can be shared and used for decision making, and in the event of a power plant accident, information necessary to maintain safety in the event of an accident can be shared and used for decision making. be able to.

In these configurations, the information transmission command unit processes control the operation parameter information of the power plant extracted by the operation parameter extraction unit at the time of the normal operation of the power plant and the initial response in the event of an accident of the power plant. It is preferable to transmit using the signal of the system, and in the event of an accident of the power plant, transmit the information of the operation parameter of the power plant extracted by the operation parameter extraction unit 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 at full throttle during normal operation of the power plant and the initial response in the event of an accident is preferably used, a part of the signal of the process control system is used in the event of an accident of the power plant. In response to the unavailability, by appropriately using the signal of the safety parameter display system that can be used at full throttle even in the event of a power plant accident, information on the operation management of the power plant can be continuously and stably transmitted. be able to.

In these configurations, it is preferable to further have a calculation interval setting unit that controls the capacity used for transmission by setting the calculation interval of the operation parameter information of the power plant extracted by the operation parameter extraction unit. According to this configuration, especially when a large capacity is used to calculate the transmission operation parameter information, the capacity used to calculate the transmission operation parameter information is limited to limit the capacity of the original power plant. While limiting the impact on the operation management support function, which is a function of the operation management support device, it is necessary to appropriately share information on the operation management of the power plant to the extent that it does not affect accurate decision making. enable.

In a configuration further including a calculation interval setting unit, the calculation interval setting unit reduces the capacity used for transmission by widening the calculation interval of the operation parameter information of the power plant extracted by the operation parameter extraction unit. It is preferable to do so. According to this configuration, by widening the time interval of the data points of the operation parameter information of the power plant, the influence on the operation management support function, which is the function of the operation management support device of the original power plant, is reduced and accurately. It enables the appropriate sharing of information on the operation management of power plants as much as necessary without affecting the decision making.

FIG. 1 is a schematic configuration diagram of a power plant in which an operation management support device for a power plant and an operation management support device for a power plant according to an embodiment of the present invention are used. FIG. 2 is a functional block diagram showing an operation management support device for the power plant of FIG. FIG. 3 is a diagram showing an operation parameter information database of 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 operation management support device of the power plant of FIG. 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 operation management support device of the power plant of FIG. 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 operation management support device of the power plant of FIG.

The operation management support device for the power plant according to the embodiment of the present invention will be described in detail below with reference to the drawings. The following description of the embodiment is not limited to the present invention, and can be modified as appropriate.

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

First, the plant security system 20 that uses the operation management support function of the operation management support device 10 of the power plant will be described below. As shown in FIG. 1, the plant security system 20 includes a power plant 22, a control device 24, and a maintenance tool 26. The control device 24 and the maintenance tool 26 are installed in the main 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 a pressure accumulator tank 38, as shown in FIG. The power plant 22 includes a thermometer 32a that measures the temperature inside the reactor 32, a water level measuring instrument 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 water, and the pressure inside the accumulator tank 38. The power plant 22 also includes various instruments and measuring instruments. Reactors 32, thermometers 32a, steam generators 34, water level measuring instruments 34a, pressurizers 36, pressure gauges 36a, accumulator tanks 38, measuring systems 38a and various other equipment and measuring instruments are used in general nuclear plants. What is used is preferably used. In the first embodiment, the power plant 22 is a nuclear power plant, but the present invention is not limited to this, and may be a thermal power plant.

The power plant 22 is electrically connected in parallel with four control units 39, which will be described later, which constitute the control device 24, so that information and communication can be performed. That is, the 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 in an information-communication manner. ing. The reactor 32, steam generator 34, pressurizer 36, accumulator tank 38, and various other devices included in the power plant 22 are provided in four control units 39 constituting the control device 24, and various parameters related to each device, etc. 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 constituting the control device 24.

Further, the thermometer 32a, the water level measuring instrument 34a, the pressure gauge 36a, the measuring system 38a and various other measuring instruments are electrically connected to the four control units 39 constituting the control device 24 so as to be capable of information communication. There is. The thermometer 32a, the water level measuring instrument 34a, the pressure gauge 36a, the measuring system 38a, and various other measuring instruments included in the power plant 22 are provided with measurement information by each measuring instrument in the four control units 39 constituting the control device 24. To send.

The control device 24 includes a plurality of control units, and specifically, as shown in FIG. 1, includes four control units 39. The control device 24 is not limited to this, and may include any number of control units. It is preferable that the control device 24 includes as many control units as possible. The four control units 39 are all device units having the same specifications. The four control units 39 are electrically connected to the power plant 22 in parallel so as to be capable of information communication. Each of the four control units 39 receives information on each device and controls the operation of the power generation plant 22 based on the received information on each device. The control device 24 processes the same control regarding the operation of the power generation plant 22 in parallel by the four control units 39.

In the plant security system 20, since the power generation plant 22 is a nuclear power plant, the control devices 24 need to be quadrupled according to the LCO (Limiting Condition of Operation). That is, in the plant security system 20, it is necessary that the control device 24 maintains a state in which the four control units 39 process the same control related to the operation of the power plant 22 in parallel. That is, in the plant security system 20, the state in which the control device 24 processes the same control related to the operation of the power plant 22 in parallel by the control units 39 having three or less is a state deviating from the LCO. Therefore, when the power plant 22 is a nuclear power plant, the control device 24 needs to include four control units 39. When the power plant 22 is a nuclear power plant, it is preferable that the control device 24 includes five or more control units 39.

The LCO is established based on the safety regulations that summarize the rules established for each type of plant. In the plant safety system 20, since the power generation plant 22 is a nuclear power plant, it is provided based on the safety regulations that summarize various rules in the nuclear power plant, but different LCOs are provided depending on the type of plant. The LCO manages the restrictions on operating conditions in a textual format regardless of the type of plant.

The four control units 39 are electrically connected to the maintenance tool 26 in parallel so as to be capable of information communication. Each of the four control units 39 transmits information on the state of the device of the control unit 39 to the maintenance tool 26. The information on the state of the device of the control unit 39 is information on whether each part of the control unit 39 is in a normal operating state or a failed state.

The four control units 39 transmit information such as various parameters related to the reactor 32, the steam generator 34, the pressurizer 36, the accumulator tank 38 and various other devices included in the power plant 22 to the maintenance tool 26. .. The four control units 39 transmit measurement information from the thermometer 32a, the water level measuring instrument 34a, the pressure gauge 36a, the measuring system 38a, and various other measuring instruments included in the power generation plant 22 to the maintenance tool 26.

Each of the control units 39 has a circuit for making a control determination of a control device 24 such as a CPU (Central Processing Unit) included in a computer. That is, each of the control units 39 performs arithmetic processing such as logic arithmetic for controlling the operation of the power plant 22. When the power plant 22 is normally operated, the control unit 39 performs arithmetic processing for controlling the normal operation within the operating conditions of the predetermined power plant 22. The operating conditions of the predetermined 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 generation plant 22, the control unit 39 controls the power generation plant 22 in response to the abnormality or accident based on the abnormality or accident information input to the control device 24. Perform arithmetic processing. For example, the control unit 39 inputs to the control device 24 that the operation of the power plant 22 is maintained and restored by a predetermined method when an abnormality or an accident that can maintain and restore the operation of the power plant 22 occurs. In response to this, arithmetic processing is performed to maintain and restore the operation of the power plant 22. Further, the control unit 39 is a control device when the power plant 22 is a pressurized water reactor and an abnormality or accident occurs in which the power plant 22 requires a reactor trip and cannot maintain and restore operation. In response to the input to the 24 to trip the reactor, the arithmetic processing for tripping the power plant 22 to the reactor is performed.

The control unit 39 preferably has a structure in which a plurality of logic calculation circuits are combined. The control unit 39 generates an instruction to control each part of the power generation plant 22 by performing the calculation set in each logic calculation circuit.

The maintenance tool 26 is an instrumentation board that collects and displays information necessary for safety protection of the power plant 22 including the reactor 32, and is sometimes called a reactor safety protection instrumentation board. The maintenance tool 26 is electrically connected in parallel to each of the four control units 39 constituting the control device 24 so that information and communication can be performed. The maintenance tool 26 receives information on the state of the device of each control unit 39 from the four control units 39. The maintenance tool 26 has a display and displays information on the state of the device of each control unit 39 on the display.

The maintenance tool 26 relates to the reactor 32, the steam generator 34, the pressurizer 36, the accumulator tank 38, and various other devices included in the power plant 22 via the four control units 39 constituting the control device 24. Receive information such as parameters. The maintenance tool 26 indicates the state of the reactor 32, the steam generator 34, the pressurizer 36, the accumulator tank 38, and various other devices included in the power plant 22 via the four control units 39 constituting the control device 24. Receive information about. The maintenance tool 26 displays the status of various devices included in the power plant 22 on the display. Specifically, when the equipment included in the power plant 22 is likely to be out of order, the maintenance tool 26 adds the equipment that is likely to be out of order to the error message or error code related to the failure. , Display on the display.

The maintenance tool 26 is provided by a thermometer 32a, a water level measuring instrument 34a, a pressure gauge 36a, a measuring system 38a, and various other measuring instruments included in the power plant 22 via four control units 39 constituting the control device 24. Receive measurement information. The maintenance tool 26 is used for the thermometer 32a, the water level measuring instrument 34a, the pressure gauge 36a, the measuring system 38a, and various other measuring instruments included in the power plant 22 via the four control units 39 constituting the control device 24. Receive status information. The maintenance tool 26 displays the status of various measuring instruments included in the power plant 22 on the display. Specifically, when the measuring instrument included in the power plant 22 has a high possibility of failure, the maintenance tool 26 displays the device having a high possibility of failure on the display.

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

Each of the four control units 39 and the maintenance tool 26 can electrically communicate with the arithmetic processing unit 11a of the control unit 11 via the information communication interface 11c of the control unit 11 in the operation management support device 10 of the power plant. Information such as various parameters related to the reactor 32, the steam generator 34, the pressurizer 36, the accumulator tank 38 and various other devices included in the power plant 22, and included in the power plant 22. The measurement information by the thermometer 32a, the water level measuring instrument 34a, the pressure gauge 36a, the measuring system 38a and various other measuring instruments 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 operation management support device 10 of the power plant is used in the plant security system 20 that secures the power plant 22, and is connected to other devices including the plant security system 20 so as to be capable of information communication. In the present embodiment, the operation management support device 10 of the power plant is a computer terminal connected by wire to other devices including the plant security system 20, but the present invention is not limited to this, and the plant security system 20 is used. It may be a portable tablet-like terminal or the like wirelessly connected to other devices including the device.

In the present embodiment, the operation management support device 10 of the power plant is a wired form that enables information communication with each part of the plant security system 20. In this case, the operation management support device 10 of the power plant does not adversely affect the equipment included in the plant safety system 20, particularly the measuring instrument having high sensitivity to radio waves. Further, since the operation management support device 10 and the plant security system 20 of the power plant do not perform wireless information communication, information is not leaked from the wireless and there is no concern about information security. Further, the operation management support device 10 of the power plant secures the plant by wire without requesting input of various information necessary for processing of the control unit 11 described later to the input unit 12 described later through the display unit 13 described later. It can be automatically obtained from the system 20.

The operation management support device 10 of the power generation plant is not limited to a form in which information communication can be performed with each part of the plant security system 20 by wire. For example, the operation management support device 10 is locked by a password or the like and the plant security system 20. It may be in a form capable of information communication with each part of the plant security system 20 by radio in a wavelength range that does not affect the equipment included in the above. In this case, since the operation management support device 10 of the power plant uses radio in a wavelength range that does not affect the devices included in the plant security system 20, adverse effects on these devices are reduced. Further, since the operation management support device 10 and the plant security system 20 of the power plant are locked to the radio, the possibility of information leakage from the radio is reduced, and the concern about information security is reduced. Further, the operation management support device 10 of the power plant automatically wirelessly transmits various information necessary for the processing of the control unit 11 from the plant security system 20 without requesting input to the input unit 12 through the display unit 13. Can be obtained.

Further, the operation management support device 10 of the power plant may be, for example, a form in which information communication with each part of the plant security system 20 is impossible, that is, a form in which stand-alone processing is performed. In this case, the operation management support device 10 of the power plant does not adversely affect the equipment included in the plant safety system 20, particularly the measuring instrument having high sensitivity to radio waves. Further, since the operation management support device 10 and the plant security system 20 of the power plant do not perform wireless information communication, information is not leaked from the wireless and there is no concern about information security. In this case, the operation management support device 10 of the power plant requests the input of various information necessary for the processing of the control unit 11 to the input unit 12 through the display unit 13, and the operator responds to the request later. It can be acquired by inputting various information such as the information displayed on the display of the maintenance tool 26 to the input unit 12.

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

The countermeasure room terminal 40 may include at least a display unit that receives information transmitted from the operation management support device 10 of the power plant and displays it in characters, images, moving images, etc. In this embodiment, the countermeasure room terminal 40 may be provided. A large display that is stationed in Tokyo and can be visually recognized by many persons engaged in the operation management of the power plant 22 at the same time is exemplified as a suitable one. In addition, the countermeasure room terminal 40 may be a plurality of personal information processing terminals given to each related party stationed in the countermeasure room. In this case, the personal information processing terminal is expensive. Functional mobile phones including mobile phones (so-called smartphones), tablet terminals, notebook or desktop PCs (Personal Computers), personal digital assistants (PDAs), and eyeglass-type and watch-type wearable devices. (Wearable Device) and the like are exemplified.

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

The input unit 12 is an interface for receiving input of various data from externally connected devices and an interface for receiving input from users. In the present embodiment, the input unit 12 is provided in the outer case of the operation management support device 10 of the power plant. Examples of the buttons, a mouse, a keyboard, and the like. 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 the information or the like that has received the 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 characters, images, moving images, and the like, and in the present embodiment, a liquid crystal display device is exemplified. The display unit 13 is not limited to this, and may be a touch panel integrated with an input device or the like.

As shown in FIG. 2, the control unit 11 includes an arithmetic processing unit 11a, a storage unit 11b, and an information communication interface 11c. In the present embodiment, the control unit 11 is exemplified as a computer having a large capacity suitable, but the present invention is not limited to this, and the control unit 11 is used for arithmetic processing of the arithmetic processing unit 11a and storage processing of the storage unit 11b, which will be described later. In addition, mobile phones including high-performance mobile phones (so-called smartphones), tablet terminals, notebook or desktop PCs, PDAs that are mobile information terminals, and glasses, as long as they have a large capacity that can withstand. A type or clock type wearable device may be used.

The arithmetic processing unit 11a is a controller, and is stored in the storage unit 11b, which is a storage device inside the operation management support device 10 of the power generation plant, by, for example, a CPU (Central Processing Unit) or an MPU (Micro Processing Unit). The various programs (corresponding to an example of an operation management support program for a power plant) are realized by executing 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 an ASIC (Application Specific Integrated Circuit) or an FPGA (Field Programmable Gate Array). The arithmetic processing unit 11a is connected to an information communication interface 11c that receives input of various data 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 with each other, and functions to control each of these components. That is, the arithmetic processing unit 11a, together with the storage unit 11b, fulfills a control function and causes the operation management support device 10 of the power plant according to the embodiment to execute the function.

As shown in FIG. 2, the arithmetic processing unit 11a includes an operation parameter extraction unit 14, an information transmission command unit 15, and a calculation interval setting unit 16. 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, is obtained by the arithmetic processing unit 11a executing the operation management support program of the power plant. , It is a functional part to be realized. The specific functions of the operation parameter extraction unit 14, the information transmission command unit 15, and the calculation interval setting unit 16 will be described later.

The arithmetic processing unit 11a also executes various computer processing related to the operation management support processing of the power plant, which is mainly executed by the operation management support device 10 of the power plant. The arithmetic processing unit 11a acquires measurement data, processing data, and the like that can be acquired from the plant safety system 20 and the power generation plant 22 via the information communication interface 11c, and refers to the image creation processing information stored in the storage unit 11b. Then, display images related to these measurement data, processing data, and the like are created, and these created display images are transmitted to the display unit 13 and the like via the information communication interface 11c and 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 the processing data that can be acquired from the plant safety system 20 and the power generation plant 22, and refers to the power generation plant 22. Each numerical value of each operation parameter related to the contents of the LCO is calculated, and the image creation processing information stored in the storage unit 11b is referred to to create a display image related to each of these calculated numerical values, and the information communication interface. These created display images are transmitted to the display unit 13 or the like via 11c and 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 operation parameter related to the calculated contents of the LCO of the power plant 22 and refers to the power plant 22. The operating state is determined, the image creation processing information stored in the storage unit 11b is referred to, a display image relating to the determined operating state is created, and these created display images are displayed via the information communication interface 11c. It is transmitted to unit 13 and the like for output.

Here, the operating state of the power plant 22 is roughly divided into two types, that is, a normal operation state in which the power plant 22 does not deviate from the LCO, and an accident state in which the power plant 22 deviates from the LCO. In addition, the operating state of the power plant 22 is roughly divided into two types at the time of an accident in which the power plant 22 deviates from the LCO, and is within the allowable standby exclusion time (Allowed Outage Time, AOT) for the deviation of the LCO. At the time of the initial response at the time of the accident where the initial response to the LCO deviation is required, and at the time of the accident where the power plant 22 is required to be stopped while responding to the accident against the LCO deviation, which is outside the allowable standby exclusion time for the deviation of the LCO. is there. That is, the operating state of the power plant 22 is roughly divided into three types, that is, during normal operation, at the time of initial response at the time of an accident, and at the time of an accident. The permissible 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 be operated.

The arithmetic processing unit 11a also refers to the corresponding processing information stored in the storage unit 11b based on the determined operating state, derives the correspondence to be applied to the power generation plant 22, and stores it in the storage unit 11b. With reference to the image creation processing information, 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 and output.

The storage unit 11b is realized by, for example, a semiconductor memory element such as a ROM (Read Only Memory), a RAM (Random Access Memory), or a flash memory (Flash Memory), or a storage device such as a hard disk or an optical disk. As shown in FIG. 2, the storage unit 11b stores and stores the operation parameter information database 17.

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

The storage unit 11b uses the storage unit 11b as various information necessary for computer processing related to the operation management support process of the power plant, for example, an operation state determination for determining the operation state of the power plant 22 based on the safety regulations of the power plant 22. Record and save information. This operating state determination information recorded and stored in the storage unit 11b is related to the contents of the LCO of the power generation plant 22 based on the measurement data and processing data that can be acquired from the plant safety system 20 and the power generation plant 22. Calculation processing information required to calculate each numerical value of each operating parameter, each numerical value such as acquireable measurement data and processing data, and each operating parameter related to the calculated LCO content of the power plant 22 Judgment processing information used for computer processing based on the allowable upper limit value, allowable lower limit value and logic such as inequality, which is necessary to judge the operating state based on each numerical value, and the power generation plant 22 based on the judged operating state. It includes correspondence processing information including judgment contents necessary for deriving the correspondence to be given to the correspondence and comparison information of the correspondence contents.

Here, the measurement data, processing data, and the like that can be acquired from the plant safety system 20 and the power plant 22 include information that the control device 24 receives input from the power plant 22 and control as information on each operation parameter of the power plant 22. Information on the control target that is controlled by the power plant 22 by being arithmetically processed by the device 24 and transmitted to the power plant 22, information on the arithmetic processing in the control device 24 that links the relationship between these information, and the like. It is included.

In addition, the storage unit 11b stores information on the periodic confirmation time regarding the time interval for automatically recording the state of the power plant 22. Further, the storage unit 11b is an image element (character information of various fonts, basic image information such as an icon, graph creation processing information, layout information) used for an image created by the arithmetic processing unit 11a and displayed on the display unit 13. , Etc.) information is stored.

The storage unit 11b automatically stores and stores various information acquired or generated by the processing by the arithmetic processing unit 11a. The storage unit 11b also automatically obtains and generates various information obtained 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 and 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 to each other by wire or wirelessly so as to be able to communicate with each other. The information communication interface 11c may connect the arithmetic processing unit 11a and the countermeasure room terminal 40 so that information communication is possible via a desired communication network.

As described above, the power plant operation management support device 10 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, the operation management of the power plant 22 is supported for a large number of related parties such as the operators and maintenance officers of the power plant 22.

The information and 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 them to the arithmetic processing unit 11a.

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

FIG. 3 is a diagram showing the operation parameter information database 17 of FIG. As shown in FIG. 3, the operation parameter information database 17 contains the operation parameters 17a and the respective necessity levels 17b and 17c at the time of normal operation, the initial response at the time of an accident, and the time of an accident, which are three types of operation states of the power plant 22. , 17d is a data collection registered in a one-to-one correspondence. Here, the necessity is the necessity of 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. It is a parameter. The degree of necessity may be calculated and registered by the arithmetic processing unit 11a based on the number of references, the degree of LCO relevance, and the like, or may be artificially input and registered from the input unit 12 by the operator. In the present embodiment, the degree of necessity is expressed by an integer of 10 steps from 1 to 10, and it is judged that the higher the numerical value, the higher the necessity, but the numerical expression method is limited to this. However, it 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. 3, is the amount of heat generated in the reactor 32, and is the amount of heat generated in the reactor 32 during normal operation. , Energy converted to electricity, and the amount of heat given to the hot effluent are related parameters. For this reason, the reactor heat output is often referred to during normal operation, so the necessity 17b is as high as 10, and the necessity 17c and 17d are both 1 because they are hardly referred to at the time of initial response at the time of an accident and at the time of an accident. It is registered 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. 3, is a negative added when all the control rods are inserted in the reactor 32. It is the reactivity of the reactor 32 and is a parameter used as an important measure indicating the magnitude of the shutdown capacity of the reactor 32. The reactivity stop margin is a parameter indicating that the higher the margin, the higher the safety. For this reason, the reactivity stop margin is often referred to as an index of safety during normal operation, so the necessity 17b is as high as 9, and it is hardly referred to during the initial response at the time of an accident and at the time of an accident. All 17d are registered as low as 1.

Control Rod Position Information, which is one of the operation parameters 17a exemplified in the operation parameter information database 17 shown in FIG. 3, is a parameter representing the position of the control rod in the reactor 32 and has a reactivity degree. This parameter is used to calculate the stop margin. For this reason, the control rod position information is often referred to as an index of safety during normal operation, so the necessity 17b is as high as 8, and it is hardly referred to at the time of initial response at the time of an accident and at the time of an accident. All 17d are 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. 3, is the Nuclear Heat Flux Hot Channel Factor, and is the nuclear heat flux hot channel factor of the reactor 32. A parameter that represents the safety coefficient that corrects the hottest fuel coolant flow path (hot channel) in consideration of the spatial distribution of the core output and the non-uniform flow of the reactor coolant in the core. is there. For this reason, FQ has a relatively high necessity of 17b of 6 because it is often referred to as an index of safety during normal operation, and it is hardly referred to at the time of initial response at the time of 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. 3, is the Nuclear Enthalpy Rise Hot Channel Factor, which is the nuclear heat flux. Similar to the hydrothermal channel coefficient, the hottest fuel coolant flow path (hot channel) takes into consideration the spatial distribution of the core output of the reactor 32 and the non-uniform flow of the reactor coolant in the core. ) Is a parameter representing a safety coefficient that corrects the minute. For this reason, FΔHN has a relatively high necessity of 17b of 6 because it is often referred to as an index of safety during normal operation, and is hardly referred to at the time of initial response at the time of an accident and at the time of an accident. Therefore, the necessity 17c and 17d 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 a departure from Nucleate Boiling Ratio, and is heated from nucleate boiling with good heat transfer efficiency. It is a parameter expressed by the value of the ratio with respect to the heat flux, that is, the departure from Nucleate Boiling, when a sudden transition to the boiling of the film whose surface is covered with a steam film occurs. For this reason, DNBR has a relatively high necessity of 17b of 6 because it is often referred to as an index of safety during normal operation, and it is hardly referred to at the time of initial response at the time of an accident and at the time of an accident. Therefore, the necessity 17c and 17d Are all registered as low as 1.

The minimum boron concentration (Minimum Boron Concentration for Shutdown), which is one of the operating parameters 17a exemplified in the operating parameter information database 17 shown in FIG. 3, is the minimum boron required to shut down the reactor 32. Concentration, which is a parameter referred to when injecting a sodium borate solution containing ¹⁰ B in order to stop the nuclear reaction in the reactor 32 at the time of initial response in the event of an accident at the power plant 22. For this reason, the minimum stop boron concentration is an important parameter that may be referred to during the initial response in the event of an accident, so the necessity 17c is as high as 10, and it is rarely referred to during normal operation and during an accident. , 17d are registered as low as 2,4 respectively.

The cooling limit, which is one of the operating parameters 17a exemplified in the operating parameter information database 17 shown in FIG. 3, is the limit at which the reactor 32 can be cooled without causing a recritical phenomenon. It is the temperature, which is a parameter that is particularly referred to at the time of initial response in the event of 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, so the necessity 17c is as high as 10, and the necessity 17d is 6 because it may be referred to in the event of an accident. Since it is relatively high and hardly referred to during normal operation, the necessity 17b is registered as low as 2.

The core monitoring information (Core Monitoring Information), which is one of the operating parameters 17a exemplified in the operating parameter information database 17 shown in FIG. 3, includes the core pressure, the average temperature of the core, and the rod cluster control (RCC). , Concentration of Boron (CB), density ρ of radioactive material accumulated in the core. Therefore, since the core monitoring information is an important parameter that may be referred to in the event of an accident in which the possibility of monitoring the reactor 32 is high, the necessity 17d is as high as 10, and it is referred to in the initial response at the time of the accident. Since there is a possibility, the necessity 17c is relatively high as 6, and the necessity 17b is registered as low as 1 because it is hardly 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. 3, is the decay heat accumulated in the core of the reactor 32, and is the reactor. It is a parameter representing the amount of heat generated by the decay of radioactive substances such as fuel in the core of 32. Immediately after the shutdown of the reactor 32, the decay heat generated by the radioactive nuclei among the products produced by the nuclear fission may reach about 5 to 6% of the reactor heat output of the reactor 32, so that the accumulator tank When an accident such as 38 or the like in which the cooling function is stopped occurs in the reactor 32, the temperature of the core of the reactor 32 rises unless the decay heat is removed by operating the decay heat removal system or the like. There is a risk that the fuel will melt. For this reason, the core decay heat is an important parameter that may be referred to at the time of initial response and accident at the time of an accident where it is highly likely that the removal of the decay heat is required, so the necessity 17c and 17d are both as high as 9. Since it is hardly referred to during normal operation, the necessity 17b is registered as low as 1.

SFP decay heat (Decay Heat from Spent Fuel Pools), which is one of the operation parameters 17a exemplified in the operation parameter information database 17 shown in FIG. 3, is SFP (Spent Fuel Pools) of the reactor 32. It is the decay heat accumulated in the fuel pool, and is a parameter representing the amount of heat generated by the decay of radioactive substances such as fuel in the spent fuel pool. For this reason, the SFP decay heat is a parameter that may be referred to in the event of an accident where it is more likely that the decay heat needs to be removed, so the necessity 17d is as high as 7, and there is a possibility that the decay heat removal is required. The necessity 17c is registered as low as 6 because it may be referred to at the time of initial response at the time of a relatively high accident, and the necessity 17b is registered as low as 1 because it is hardly referred to during normal operation.

The core reactivity (Core Reactivity), which is one of the operating parameters 17a exemplified in the operating parameter information database 17 shown in FIG. 3, is a dimensionless amount indicating the degree to which the reactor 32 deviates from the critical state. Yes, for example, the excess multiplication factor of neutrons is divided by the effective multiplication factor of neutrons, the critical state of the reactor 32 is represented by 0, and the critical 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 amount of neutrons generated by nuclear fission in the reactor 32 is continuously balanced between the amount contributing to the next nuclear fission and the amount escaping from the system. .. Therefore, the reactivity of the core is a relatively high necessity 17d of 6 because it is an important parameter that may be referred to in the event of an accident in which the reactor 32 is likely to be in a critical state or an overcritical state. The necessity 17c is registered as low as 1 because it may be referred to at the time of initial response at the time of an accident, and it is hardly referred to during normal operation to the extent that the necessity 17c is neither high nor low.

In the operation parameter information database 17 shown in FIG. 3, the above-mentioned operation parameter 17a is illustrated, but it is preferable that other operation parameters 17a not exemplified are further included. When other operation parameters 17a are further included, these operation parameters 17a are registered in a one-to-one correspondence with the respective necessity levels 17b, 17c, 17d in the same manner as the above-mentioned operation parameters 17a. Further, each necessity 17b, 17c, 17d is arbitrarily determined, and the values shown in the present specification and FIG. 3 are examples.

The operation parameter extraction unit 14 included in the arithmetic processing unit 11a extracts the operation parameters of the power plant 22 based on the necessity of determining the operation management of the power plant 22. Specifically, it is preferable that the operation parameter extraction unit 14 extracts a predetermined number of operation parameters of the power plant 22 in descending order of necessity of determination of operation management of the power plant 22. Further, it is preferable that the operation parameter extraction unit 14 extracts the operation parameters of different power generation plants 22 according to the operation status of the power generation plant 22.

More specifically, the operation parameter extraction unit 14 refers to the operation parameter information database 17 stored and stored in the storage unit 11b, and refers to the initial operation during normal operation and accident, which are three types of operation states of the power plant 22. The operating parameters 17a of the power plant 22 of about 3 or more and 6 or less are extracted in descending order of each necessity 17b, 17c, 17d for each of the response time and the accident time.

For example, when referring to the operation parameter information database 17 shown in FIG. 3, the operation parameter extraction unit 14 sets the operation parameter 17a of the power plant 22 as the operation parameter 17a of the power plant 22 during the normal operation of the power plant 22, and sets the reactor heat output and the reactivity stop margin. And control rod position information is extracted. Further, the operation parameter extraction unit 14 sets the minimum stop boron concentration, the coolable temperature, and the decay heat (= core decay heat) as the operation parameter 17a of the power plant 22, for example, at the time of the initial response in the event of an accident of the power plant 22. Is extracted. Further, for example, in the event of an accident at the power generation plant 22, the operation parameter extraction unit 14 sets the operating parameter 17a of the power generation plant 22 as the reactivity of the core, radioactive substances accumulated in the core, and decay heat (= core decay heat and SFP). (Collapse heat) is extracted. In the normal operation of the power plant 22, the operation parameter extraction unit 14 relatively suppresses the load such as the capacity applied to the operation management support device 10 of the power plant as compared with the initial response at the time of the accident and the time of the accident. Therefore, the number of operating parameters 17a to be extracted may be increased. In this case, FQ, FΔHN and DNBR are additionally extracted in addition to the reactor heat output, the reactivity stop margin and the control rod position information. You may.

The information transmission command unit 15 included in the arithmetic processing unit 11a transmits the information of the operation parameter 17a of the power plant 22 extracted by the operation parameter extraction unit 14. 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 parameter 17a of the power plant 22 extracted by the operation parameter extraction unit 14. Therefore, a display image relating to the operation parameter 17a of these power plants 22 is created. Next, the information transmission command unit 15 uses the information communication interface 11c to create the display images (for example, the first display screen 53, the second display screen 54, and the third display image shown in FIGS. 4, 5 and 6). The display screen 55) is transmitted to the countermeasure room terminal 40 and displayed on the display unit of the countermeasure room terminal 40. The 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 operation management support device 10 of the power generation plant including the information communication path from the operation management support device 10 of the power plant to the countermeasure room terminal 40 is a process control system (for information communication). It is preferable to use the signal of the Process Control Computer System (PCCS) (hereinafter referred to as the PCCS signal) and the signal of the safety parameter display system (SPDS) (hereinafter referred to as the SPDS signal) in combination.

The process control system is a control computer system, which is a system composed of a computer and peripheral equipment used for controlling and monitoring the operation parameter 17a of the power generation plant 22. The PCCS signal is a signal used for information communication in such a process control system. The safety parameter display system is a kind of permanent serious accident mitigation equipment of the power plant 22, and is 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 a signal used for information communication in such a safety parameter display system. The SPDS signal can be suitably used when the PCCS signal is interrupted due to an accident at the power plant 22 or the like.

When such an information communication system is used around the operation management support device 10 of the power plant, the information transmission command unit 15 is used during the normal operation of the power plant 22 and the initial response in the event of an accident at the power plant 22. Information on the operation parameter 17a of the power plant 22 extracted by the operation parameter extraction unit 14 is transmitted using the PCCS signal, and in the event of an accident at the power plant 22, the operation parameter 17a of the power plant 22 extracted by the operation parameter extraction unit 14 is transmitted. It is preferable to transmit the information using the SPDS signal.

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

When calculating the operation parameter 17a, the arithmetic processing unit 11a uses the capacity of the RAM in which the CPU, MPU, or the like is the work area, depending on the calculation method of the operation parameter 17a or the like. Therefore, the calculation interval setting unit 16 is used for the calculation of the operation parameter 17a by the arithmetic processing unit 11a by controlling the calculation interval of the information of the operation parameter 17a, that is, by controlling the time interval, the space interval, and the like. It is possible to control the capacity to be generated. Further, the calculation interval setting unit 16 increases the calculation interval of the information of the operation parameter 17a, that is, the capacity used for the calculation of the operation parameter 17a by the arithmetic processing unit 11a by expanding the time interval, the space interval, and the like. Can be reduced. The capacity used for the calculation of the operation parameter 17a by the arithmetic processing unit 11a is a part of the capacity used for transmitting the information of the operation parameter 17a.

The information communication path from the operation management support device 10 of the power plant to the countermeasure room terminal 40 uses a capacity based on the capacity of the information to be transmitted when transmitting the information of the operation parameter 17a. Therefore, the calculation interval setting unit 16 controls the calculation interval of the information of the operation parameter 17a, that is, the capacity of the information of the operation parameter 17a provided for transmission by controlling the time interval, the space interval, and the like. Can be controlled to control the capacity used in the information communication path from the operation management support device 10 of the power plant to the countermeasure room terminal 40. Further, the calculation interval setting unit 16 reduces the capacity of the information of the operation parameter 17a provided for transmission by widening the calculation interval of the information of the operation parameter 17a, that is, by widening the time interval, the space interval, and the like. Therefore, the capacity used in the information communication path from the operation management support device 10 of the power plant to the countermeasure room terminal 40 can be reduced. The capacity used in the information communication path from the operation management support device 10 of the power plant to the countermeasure 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 sets and changes the time interval for calculating the information of the operation parameter 17a to 12 hours, so that information communication is performed when transmitting the capacity used for the calculation of the operation parameter 17a and the information of the operation parameter 17a. The capacity used in the route can be suitably reduced.

FIG. 4 is a diagram showing a first display screen 53, which is an example of a screen displayed by the operation management support device 10 of the power plant of FIG. 1 on the display unit of the countermeasure room terminal 40. FIG. 5 is a diagram showing a second display screen 54, which is an example of a screen displayed by the operation management support device 10 of the power plant of FIG. 1 on the display unit of the countermeasure room terminal 40. FIG. 6 is a diagram showing a third display screen 55, which is an example of a screen displayed by the operation management support device 10 of the power plant of FIG. 1 on the display unit of the countermeasure room terminal 40. In the following, an example of a screen displayed on the display unit of the countermeasure room terminal 40 by the operation management support device 10 of the power plant will be described with reference to FIGS. 4, 5 and 6.

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. 4, 5 and 6, and will be described later. Displayed so that they can be switched between each other. The present invention is not limited to this, and the display form of the screen can be changed as appropriate. The scales and values shown in FIGS. 4, 5 and 6 are typical examples.

As shown in FIGS. 4, 5 and 6, the display screen 50 having a frame structure extends over a header screen portion 51 provided at the upper part and a portion below the header screen portion 51 excluding the header screen portion 51. It has a main screen portion 52 provided.

The header screen unit 51 is common to any of the first display screen 53, the second display screen 54, and the third display screen 55, and as shown in FIGS. 4, 5, and 6, the header screen unit 51 is common. From the left side of the screen unit 51, the power plant name display 51a, the monitoring status display 51b, and the time display 51c are provided in this order. The power plant name display 51a displays the name of the power plant 22. The monitoring status display 51b indicates whether or not the power plant 22 having the name displayed on the power plant name display 51a is being monitored, and if it is in the monitoring state, monitoring is performed. Display as medium. The monitoring status display 51b displays, for example, non-monitoring in the case of a non-monitoring state. The time display 51c displays the current time.

The main screen unit 52 is a portion in which the first display screen 53, the second display screen 54, and the third display screen 55 are embedded, respectively, and as shown in FIGS. 4, 5 and 6, in order from the upper left side. The first tab 52a that displays the first display screen 53 by accepting the selection, the second tab 52b that displays the second display screen 54 by accepting the selection, and the third display screen 55 by accepting the selection are displayed. It has a third tab 52c and the like. Therefore, regardless of which of the first display screen 53, the second display screen 54, and the third display screen 55 is embedded and displayed in the main screen unit 52, the main screen unit can be selected by selecting the first tab 52a. The screen embedded in the 52 can be switched to the first display screen 53, and the screen embedded in the main screen portion 52 can be switched to the second display screen 54 by selecting the second tab 52b, and the third tab 52c can be switched. By selecting, the screen embedded in the main screen unit 52 can be switched to the third display screen 55.

The first tab 52a displays the character string of the main LCO, which is a matter to be confirmed during the normal operation of the power plant 22, and when this is selected, the operation parameter extraction unit 14 performs the operation parameter extraction unit 14 during the normal operation of the power plant 22. The screen switches to the first display screen 53 for displaying the operation parameter 17a of the extracted power plant 22.

As shown in FIG. 4, the first display screen 53 shows the reactor heat output, reactivity stop margin, and control, which are the operation parameters 17a of the power plant 22 extracted by the operation parameter extraction unit 14 during the normal operation of the power plant 22. The rod position information, FQ, FΔHN, and DNBR are arranged and displayed at each display portion 53a, 53b, 53c, 53d, 53e, 53f. Among the operation parameters 17a of the power plant 22, the first display screen 53 displays the reactor heat output, the reactivity stop margin, and the control rod position information, which are highly necessary for the judgment of the operation management of the power plant 22. The display parts 53a, 53b, and 53c in the upper row are arranged and displayed.

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

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

The second tab 52b displays a character string of a parameter for stopping the plant, which is a matter to be confirmed at the time of the initial response at the time of the accident of the power plant 22. By selecting this, the initial response at the time of the accident of the power plant 22 is displayed. The time is switched to the second display screen 54 that displays the operation parameter 17a of the power plant 22 extracted by the operation parameter extraction unit 14.

As shown in FIG. 5, the second display screen 54 has a minimum stop boron concentration, which is the operation parameter 17a of the power plant 22 extracted by the operation parameter extraction unit 14 for the initial response in the event of an accident of the power plant 22, and can be cooled. The temperature, core decay heat, and core reactivity are arranged and displayed at the respective display sites 54a, 54b, 54c, and 54d. Further, on the second display screen 54, in addition to displaying the core decay heat numerically at the display portion 54c, the second display screen 54 also displays a graph at the display portion 54e. The second display screen 54 shows the minimum stop boron concentration, the cooling temperature, and the core collapse so that many persons who are stationed in the countermeasure room and engaged in the operation management of the power plant 22 can clearly judge the initial response. The heat is displayed numerically for each situation. The second display screen 54 is provided so that many persons who are stationed in the countermeasure room and engaged in the operation management of the power plant 22 can easily understand the time change of the situation of the reactor 32 of the power plant 22 at a glance. , The reactivity of the core is displayed in a graph, and the information on the criticality is displayed superimposed on this graph.

The third tab 52c displays a character string for accident monitoring, which is a matter to be confirmed in the event of an accident in the power plant 22, and when this is selected, the operation parameter extraction unit 14 extracts the accident in the power plant 22. The screen switches to the third display screen 55 that displays the operation parameter 17a of the power plant 22.

As shown in FIG. 5, the third display screen 55 displays core information, core decay heat, and SFP decay heat, which are the operation parameters 17a of the power plant 22 extracted by the operation parameter extraction unit 14 at the time of the accident of the power plant 22. The display parts 55a, 55b, and 55c are arranged and displayed. Since the third display screen 55 is a screen after the response at the time of the accident, the core monitoring information is displayed on the display portion 55a, but it is highly necessary information before the response at the time of the accident. , It is preferable that the same information as the reactivity of the core displayed on the display portion 54d of the second display screen 54 is displayed. The core monitoring information displayed on the display site 55a includes core pressure [unit: MPa], core average temperature [unit: ° C], rod cluster control (RCC) [unit; Step], and boron concentration (CB) [unit]. ; Ppm], the density ρ [unit; ppm] of the radioactive material accumulated in the core. In the graphs of the core decay heat and SFP decay heat information shown in the display parts 55b and 55c, respectively, many people who are stationed in the countermeasure room and engaged in the operation management of the power plant 22 indicate the safety of the core. Safety analysis conditions are shown in layers to make it easier to make a clear decision.

As described above, the power plant operation management support device 10 selects and transmits the information of the power plant 22 operation parameter 17a extracted based on the necessity of the power plant 22 operation management judgment, so that the power plant Information on the operation management of 22 can be appropriately shared as much as necessary. As a result, the power plant operation management support device 10 makes it possible to promptly execute an accurate decision-making regarding countermeasures and the like based on the information on the operation management of the power plant 22 in an appropriate amount.

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

Further, in the operation management support device 10 of the power plant, the operation parameter extraction unit 14 extracts the operation parameters 17a of different power plants 22 according to the operation status of the power plant 22. Therefore, the operation management support device 10 of the power plant can select and share necessary information according to the operation status of the power plant 22, and based on the information selected according to the operation status of the power plant 22. Allows you to make accurate decisions quickly.

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

Further, in the power plant operation management support device 10, when the information transmission command unit 15 performs the normal operation of the power plant 22 and the initial response in the event of an accident of the power plant 22, the operation parameter extraction unit 14 extracts the power plant 22. Information on the operation parameter 17a is transmitted using the signal of the process control system, and in the event of an accident at the power plant 22, the information on the operation parameter 17a of the power plant 22 extracted by the operation parameter extraction unit 14 is transmitted as a signal of the safety parameter display system. Use to send. Therefore, the operation management support device 10 of the power plant preferably uses the signal of the process control system that can be used at full throttle during the normal operation of the power plant 22 and the initial response in the event of an accident, and at the time of the accident of the power plant 22. Operation management of the power plant 22 by appropriately using the signal of the safety parameter display system that can be used at full throttle even in the event of an accident at the power plant 22 in response to the fact that some of the signals of the process control system cannot be used Information about can be continuously and stably transmitted.

Further, the power plant operation management support device 10 sets the calculation interval for controlling the capacity used for transmission by setting the calculation interval of the information of the operation parameter 17a of the power plant 22 extracted by the operation parameter extraction unit 14. It further has a portion 16. Therefore, when the operation management support device 10 of the power plant uses a large capacity for calculating the information of the operation parameter 17a for transmission, the capacity used for calculating the information of the operation parameter 17a for transmission is limited. By doing so, information on the operation management of the power plant 22 is limited to the extent that it does not affect accurate decision making while limiting the influence on the operation management support function which is the function of the operation management support device 10 of the original power plant. Allows you to properly share as much as you need.

Further, in the power plant operation management support device 10, the calculation interval setting unit 16 expands the calculation interval of the information of the operation parameter 17a of the power plant 22 extracted by the operation parameter extraction unit 14, so that the capacity used for transmission is increased. To reduce. Therefore, the operation management support device 10 of the power plant increases 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 is a function of the operation management support device 10 of the original power plant. It makes it possible to appropriately share information on the operation management of the power plant 22 as much as necessary while reducing the influence on the function and not affecting accurate decision making.

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 Parameters 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 Accumulation tank 38a Measuring system 39 Control unit 40 Countermeasure room terminal 50 Display screen 51 Header screen 51a Power plant name display 51b Monitoring status display 51c Time display 52 Main screen 52a 1st tab 52b 2nd tab 52c 3rd tab 53 1st 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 (7)

A power plant operation management support device that supports the operation management of a power plant.
An operation parameter extraction unit that extracts operation parameters of the power plant based on the necessity of judgment of operation management of the power plant, and an operation parameter extraction unit.
An information transmission command unit that transmits information on the operation parameters of the power plant extracted by the operation parameter extraction unit, and
An operation management support device for a power plant, which is characterized by being equipped with. The operation management of the power plant according to claim 1, wherein the operation parameter extraction unit extracts a predetermined number of operation parameters of the power plant in descending order of necessity for determination of operation management of the power plant. Support device. The operation management support device for a power plant according to claim 1 or 2, wherein the operation parameter extraction unit extracts different operation parameters of the power plant according to the operation status of the power plant. The operation parameter extraction unit
During normal operation of the power plant, reactor heat output, reactivity stop margin and control rod position information are extracted as operating parameters of the power plant.
For the initial response in the event of an accident at the power plant, the minimum stop boron concentration, coolable temperature, and decay heat are extracted as operating parameters of the power plant.
The operation management support device for a power plant according to claim 3, wherein core monitoring information, core decay heat, and SFP decay heat are extracted as operation parameters of the power plant in the event of an accident at the power plant. The information transmission command unit uses the signal of the process control system for the information of the operation parameters of the power plant extracted by the operation parameter extraction unit at the time of the normal operation of the power plant and the initial response at the time of the accident of the power plant. 1. In the event of an accident at the power plant, the operation parameter information of the power plant extracted by the operation parameter extraction unit is transmitted using a signal of the safety parameter display system. The operation management support device for a power plant according to any one of claim 4. According to claim 1, the calculation interval setting unit for controlling the capacity used for transmission is further provided by setting the calculation interval of the operation parameter information of the power plant extracted by the operation parameter extraction unit. The operation management support device for a power plant according to any one of claims 5. 6. The calculation interval setting unit is characterized in that the capacity used for transmission is reduced by widening the calculation interval of the operation parameter information of the power plant extracted by the operation parameter extraction unit. The operation management support device of the power plant described.

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