CN117711650A - Nuclear reactor monitoring method, device, computer equipment and storage medium - Google Patents
Nuclear reactor monitoring method, device, computer equipment and storage medium Download PDFInfo
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Abstract
The present application relates to a nuclear reactor monitoring method, apparatus, computer device, storage medium and computer program product. The method comprises the following steps: acquiring voltage monitoring values respectively corresponding to at least two monitoring areas of a target nuclear reactor; the voltage monitoring value is acquired by a neutron detector in the monitoring area; converting the voltage monitoring value acquired by the neutron detector into a neutron counting monitoring value based on the monitoring range information corresponding to the neutron detector, and obtaining neutron counting monitoring values corresponding to all monitoring areas respectively; comparing neutron count monitoring values and neutron count early warning values corresponding to the same monitoring area to respectively obtain nuclear reactor states corresponding to all the monitoring areas; and displaying the nuclear reactor states corresponding to the monitoring areas respectively. The method can improve the monitoring efficiency of the nuclear reactor.
Description
Technical Field
The present application relates to the field of computer technology, and in particular, to a nuclear reactor monitoring method, apparatus, computer device, storage medium, and computer program product.
Background
During overhaul and refueling of a nuclear power plant, source range neutron flux of a refueling site needs to be continuously monitored, whether the refueling site is abnormal or not is determined based on measurement signals acquired by a neutron detector, and when the abnormality occurs, the nuclear power plant is stopped in time, so that the occurrence of unexpected critical accidents is prevented.
The current monitoring method is to read and display the voltage measurement signal of the neutron detector through a recorder, and the staff determines the state of the nuclear reactor according to the voltage measurement signal displayed by the recorder, so that the problem of low monitoring efficiency of the nuclear reactor exists.
Disclosure of Invention
In view of the foregoing, it is desirable to provide a nuclear reactor monitoring method, apparatus, computer device, computer-readable storage medium, and computer program product that can improve the efficiency of nuclear reactor condition monitoring.
A nuclear reactor monitoring method is provided. The method comprises the following steps:
acquiring voltage monitoring values respectively corresponding to at least two monitoring areas of a target nuclear reactor; the voltage monitoring value is acquired by a neutron detector in the monitoring area;
converting the voltage monitoring value acquired by the neutron detector into a neutron counting monitoring value based on the monitoring range information corresponding to the neutron detector, and obtaining neutron counting monitoring values corresponding to all monitoring areas respectively;
Comparing neutron count monitoring values and neutron count early warning values corresponding to the same monitoring area to respectively obtain nuclear reactor states corresponding to all the monitoring areas;
and displaying the nuclear reactor states corresponding to the monitoring areas respectively.
The application also provides a nuclear reactor monitoring device. The device comprises:
the voltage monitoring value acquisition module is used for acquiring voltage monitoring values corresponding to at least two monitoring areas of the target nuclear reactor respectively; the voltage monitoring value is acquired by a neutron detector in the monitoring area;
the neutron count value conversion module is used for converting the voltage monitoring value acquired by the neutron detector into a neutron count monitoring value based on the monitoring range information corresponding to the neutron detector, so as to obtain neutron count monitoring values corresponding to all monitoring areas respectively;
the nuclear reactor state determining module is used for comparing the neutron count monitoring value and the neutron count early warning value corresponding to the same monitoring area to respectively obtain the nuclear reactor states corresponding to the monitoring areas;
and the nuclear reactor state display module is used for displaying the nuclear reactor states respectively corresponding to the monitoring areas.
A computer device comprising a memory storing a computer program and a processor implementing the steps of the nuclear reactor monitoring method described above when the processor executes the computer program.
A computer readable storage medium having stored thereon a computer program which, when executed by a processor, performs the steps of the nuclear reactor monitoring method described above.
A computer program product comprising a computer program which, when executed by a processor, performs the steps of the nuclear reactor monitoring method described above.
The nuclear reactor monitoring method, the device, the computer equipment, the storage medium and the computer program product are used for acquiring voltage monitoring values respectively corresponding to at least two monitoring areas of a target nuclear reactor, wherein the voltage monitoring values are acquired through neutron detectors in the monitoring areas. Based on the monitoring range information corresponding to the neutron detector, converting the voltage monitoring value acquired by the neutron detector into a neutron counting monitoring value to obtain neutron counting monitoring values corresponding to all monitoring areas respectively. And comparing the neutron count monitoring value and the neutron count early warning value corresponding to the same monitoring area to respectively obtain the nuclear reactor states corresponding to the monitoring areas, and displaying the nuclear reactor states corresponding to the monitoring areas. Therefore, according to the monitoring range information corresponding to the neutron detector, the voltage monitoring values corresponding to the monitoring areas are converted into corresponding neutron counting monitoring values, and further according to the neutron counting monitoring values and neutron counting early warning values corresponding to the same monitoring area, the nuclear reactor state corresponding to the monitoring areas can be rapidly and accurately determined, and therefore the nuclear reactor monitoring efficiency is improved.
Drawings
FIG. 1 is a diagram of an application environment for a nuclear reactor monitoring method in one embodiment;
FIG. 2 is a flow diagram of a method of nuclear reactor monitoring in one embodiment;
FIG. 3 is a flow chart of converting voltage monitoring values to neutron count monitoring values in one embodiment;
FIG. 4 is a schematic diagram of an early warning value adjustment page in one embodiment;
FIG. 5 is a schematic diagram of a neutron display in one embodiment;
FIG. 6 is a schematic diagram of a neutron display in one embodiment;
FIG. 7 is a flow diagram of nuclear reactor monitoring in another embodiment;
FIG. 8 is a block diagram of a nuclear reactor monitoring device in one embodiment;
FIG. 9 is a block diagram of another embodiment nuclear reactor monitoring device;
fig. 10 is an internal structural view of a computer device in one embodiment.
Detailed Description
In order to make the objects, technical solutions and advantages of the present application more apparent, the present application will be further described in detail with reference to the accompanying drawings and examples. It should be understood that the specific embodiments described herein are for purposes of illustration only and are not intended to limit the present application.
The nuclear reactor monitoring method provided by the embodiment of the application can be applied to an application environment shown in fig. 1. Wherein the terminal 102 communicates with the neutron detector 104. The terminal 102 may be, but not limited to, various single-chip computers, personal computers, notebook computers, smart phones, tablet computers, internet of things devices, and portable wearable devices, and the internet of things devices may be smart televisions, smart vehicle devices, and the like. The portable wearable device may be a smart watch, smart bracelet, headset, or the like. The terminal 102 and the neutron detector 104 may be directly or indirectly connected by wired or wireless communication, which is not limited herein.
The nuclear reactor monitoring method provided in the embodiments of the present application may be performed by a terminal.
For example, the terminal acquires voltage monitoring values respectively corresponding to at least two monitoring areas of the target nuclear reactor; the voltage monitoring value is acquired by neutron detectors in the monitored area. The terminal converts the voltage monitoring value acquired by the neutron detector into a neutron counting monitoring value based on the monitoring range information corresponding to the neutron detector, and obtains the neutron counting monitoring value corresponding to each monitoring area. And the terminal compares the neutron count monitoring value and the neutron count early warning value corresponding to the same monitoring area to respectively obtain the nuclear reactor states corresponding to the monitoring areas. And the terminal displays the nuclear reactor states corresponding to the monitoring areas respectively.
In one embodiment, as shown in fig. 2, a nuclear reactor monitoring method is provided, which is applied to a terminal for illustration, and includes the following steps:
step S202, voltage monitoring values respectively corresponding to at least two monitoring areas of a target nuclear reactor are obtained; the voltage monitoring value is acquired by neutron detectors in the monitored area.
The target nuclear reactor is a nuclear reactor to be monitored, a plurality of monitoring areas are arranged in the nuclear reactor, and the neutron detectors arranged in the monitoring areas are used for monitoring the states of the nuclear reactor in each monitoring area in real time. The neutron detector is used for detecting the number of neutrons in the monitoring area, outputting corresponding current signals, and converting the current signals into required voltage measurement signals through the precision resistor. In an actual implementation process, each neutron source assembly in the target nuclear reactor corresponds to a monitoring area, and at least one neutron detector is arranged for the monitoring area corresponding to each neutron source assembly in the target nuclear reactor. The voltage monitoring value refers to a voltage measurement signal obtained by detecting a monitoring area by a neutron detector.
Illustratively, each neutron detector in the target nuclear reactor continuously monitors the number of neutrons in a corresponding monitoring region, respectively, and outputs a voltage monitoring value. The terminal acquires voltage monitoring values respectively acquired by each neutron detector in the target nuclear reactor, and safety monitoring on the target nuclear reactor is realized based on the voltage monitoring values respectively corresponding to each monitoring area.
Step S204, based on the monitoring range information corresponding to the neutron detector, converting the voltage monitoring value acquired by the neutron detector into a neutron counting monitoring value to obtain neutron counting monitoring values corresponding to all monitoring areas respectively.
The monitoring range information refers to a corresponding measurement range of the neutron detector, and includes at least one of a range of voltage measurement signals output by the neutron detector, a range of current measurement signals output by the neutron detector and a range of neutron quantity which can be measured by the neutron detector. The neutron count monitoring value is the neutron number corresponding to the obtained voltage monitoring value after the voltage monitoring value is converted.
For example, for a voltage monitoring value collected by any neutron detector in a target nuclear reactor, the terminal acquires monitoring range information corresponding to the neutron detector, converts the voltage monitoring value collected by the neutron detector into a reference voltage value based on a voltage monitoring range in the monitoring range information corresponding to the neutron detector, and further maps the reference voltage value to a neutron counting monitoring range in the monitoring range information to obtain a corresponding neutron counting monitoring value.
Step S206, comparing the neutron count monitoring value and the neutron count early warning value corresponding to the same monitoring area to respectively obtain the nuclear reactor states corresponding to the monitoring areas.
The neutron counting early warning value is an early warning value set for the neutron counting monitoring value in the pointer, and if the neutron counting monitoring value exceeds the neutron counting early warning value, the nuclear reactor state corresponding to the monitoring area is determined to be an abnormal state. The nuclear reactor state refers to an operating state of a nuclear reactor within a monitoring area.
For example, when the neutron count monitoring value corresponding to the monitoring area is smaller than the neutron count early warning value corresponding to the monitoring area, the terminal determines that the nuclear reactor state corresponding to the monitoring area is in a normal state. When the neutron count monitoring value corresponding to the monitoring area is larger than or equal to the neutron count early warning value corresponding to the monitoring area, the terminal determines that the nuclear reactor state corresponding to the monitoring area is abnormal, and triggers an abnormal alarm aiming at the monitoring area.
Step S208, displaying the nuclear reactor states corresponding to the monitoring areas respectively.
The terminal displays the monitoring area identification, the nuclear reactor state and the neutron count monitoring value corresponding to each monitoring area respectively. In the actual implementation process, the monitoring data of the monitoring area in the normal state can be displayed in a conventional display mode, and the monitoring data corresponding to the monitoring area in the abnormal state can be highlighted. For example, when a monitoring area in an abnormal state appears, the monitoring area identifier corresponding to the monitoring area is highlighted, and other monitoring data are displayed in a conventional mode, so that a worker can quickly locate the monitoring area in the abnormal state, and meanwhile, normal display of other monitoring data is guaranteed, so that the worker can conveniently read the monitoring area.
In the above nuclear reactor monitoring method, the voltage monitoring values respectively corresponding to at least two monitoring areas of the target nuclear reactor are acquired through neutron detectors in the monitoring areas. Based on the monitoring range information corresponding to the neutron detector, converting the voltage monitoring value acquired by the neutron detector into a neutron counting monitoring value to obtain neutron counting monitoring values corresponding to all monitoring areas respectively. And comparing the neutron count monitoring value and the neutron count early warning value corresponding to the same monitoring area to respectively obtain the nuclear reactor states corresponding to the monitoring areas, and displaying the nuclear reactor states corresponding to the monitoring areas. Therefore, according to the monitoring range information corresponding to the neutron detector, the voltage monitoring values corresponding to the monitoring areas are converted into corresponding neutron counting monitoring values, and further according to the neutron counting monitoring values and neutron counting early warning values corresponding to the same monitoring area, the nuclear reactor state corresponding to the monitoring areas can be rapidly and accurately determined, and therefore the nuclear reactor monitoring efficiency is improved.
In one embodiment, as shown in fig. 3, based on monitoring range information corresponding to the neutron detector, converting a voltage monitoring value collected by the neutron detector into a neutron count monitoring value, to obtain neutron count monitoring values corresponding to each monitoring area, including:
Step S302, aiming at a neutron detector in a current monitoring area, converting a voltage monitoring value corresponding to the current monitoring area into a reference voltage value based on a voltage monitoring range in monitoring range information corresponding to the neutron detector; the reference voltage value is used for indicating the position of the voltage monitoring value corresponding to the current monitoring area in the voltage monitoring range.
And step S304, mapping the reference voltage value into a neutron count monitoring value based on the neutron count monitoring range in the monitoring range information, and obtaining the neutron count monitoring value corresponding to the current monitoring area.
The current monitoring area refers to any monitoring area which needs to convert a voltage monitoring value into a neutron counting monitoring value in each monitoring area corresponding to the target nuclear reactor. The voltage monitoring range refers to a range of outputting a required voltage measurement signal after a current signal of the neutron detector passes through a precision resistor, and for example, the voltage monitoring range can be 1-5V. The neutron count monitoring range refers to a range of the number of neutrons that the neutron detector can detect, e.g., the neutron count monitoring range mayIs 1 to 1.6×cps。
The terminal takes any monitoring area in the target nuclear reactor as the current monitoring area, acquires a voltage monitoring range from monitoring range information corresponding to the neutron detector in the current monitoring area, and determines a voltage range corresponding to the neutron detector based on the voltage monitoring range. And comparing the difference between the voltage monitoring value and the voltage minimum value in the voltage monitoring range with the voltage measuring range to obtain a reference voltage value corresponding to the voltage monitoring value. And further acquiring a neutron count monitoring range from the monitoring range information, and converting the reference voltage value into a neutron count monitoring value corresponding to the current monitoring area according to the mapping relation between the reference voltage value and the neutron count monitoring value.
In one embodiment, the neutron count monitor value may be calculated by the following formula:
wherein c is a neutron count monitoring value, v is a voltage monitoring value,for the lower voltage limit in the voltage monitoring range, < +.>For the upper voltage limit in the voltage monitoring range, < +.>For neutron count lower limit value in neutron count monitoring range,/->For neutron count upper limit value in neutron count monitoring range,/->Is the reference voltage value.
In the above embodiment, according to the voltage monitoring range in the monitoring range information corresponding to the neutron detector, the voltage monitoring value is converted into the reference voltage value, and then, based on the mapping relationship between the reference voltage value and the neutron counting monitoring value, the reference voltage value is converted into the corresponding neutron counting monitoring value, so that the voltage monitoring value can be quickly and accurately converted into the corresponding neutron counting monitoring value. And then confirm the corresponding nuclear reactor state of monitoring area based on neutron count monitoring value and neutron count early warning value, can improve the early warning accuracy to improve nuclear reactor monitoring efficiency.
In one embodiment, comparing neutron count monitoring values and neutron count early warning values corresponding to the same monitoring region to obtain nuclear reactor states corresponding to the monitoring regions respectively includes:
Determining a nuclear reactor state corresponding to a monitoring area with a neutron counting monitoring value larger than a neutron counting early warning value as an abnormal state, and determining a nuclear reactor state corresponding to a monitoring area with a neutron counting monitoring value smaller than or equal to the neutron counting early warning value as a normal state to obtain a nuclear reactor state corresponding to each monitoring area respectively; the nuclear reactor status is used for indicating an abnormality alarm for the monitoring area.
The terminal converts the voltage monitoring value corresponding to the current monitoring area into a corresponding neutron counting monitoring value, and then compares the neutron counting monitoring value with a neutron counting early warning value corresponding to the current monitoring area. If the neutron count monitoring value is larger than the corresponding neutron count early warning value, determining that the nuclear reactor state corresponding to the current monitoring area is abnormal, and if the neutron count monitoring value is smaller than or equal to the corresponding neutron count early warning value, determining that the nuclear reactor state corresponding to the current monitoring area is normal. And triggering an abnormal alarm aiming at the current monitoring area if the nuclear reactor state corresponding to the current monitoring area is an abnormal state. In the actual implementation process, the alarm voice corresponding to each monitoring area can be generated based on the area identifier corresponding to each monitoring area, when the monitoring area in an abnormal state appears, the alarm voice corresponding to the monitoring area is triggered, and the monitoring area is highlighted. For example, an alarm voice for the monitoring area is played, and an area identifier corresponding to the monitoring area is highlighted. In addition, corresponding early warning information can be generated based on data such as the area identifier, the voltage monitoring value, the neutron count early warning value and the like corresponding to the monitoring area in the abnormal state, and the early warning information is sent to the terminal of the staff.
In the above embodiment, when the neutron count monitoring value corresponding to the current monitoring area is greater than the neutron count early warning value corresponding to the current monitoring area, the state of the nuclear reactor corresponding to the current monitoring area is determined to be an abnormal state, and an abnormal alarm aiming at the current monitoring area is triggered, so that staff can take countermeasures in time, the efficiency of nuclear reactor monitoring is improved, and the safety of the nuclear reactor is ensured.
In one embodiment, the nuclear reactor monitoring method further comprises:
responding to monitoring area selection operation aiming at an operation control, determining areas to be regulated in each monitoring area, and displaying an early warning value regulating page corresponding to the areas to be regulated; responding to the early warning value adjusting operation aiming at the operation control, and displaying a standard counting early warning value corresponding to the area to be adjusted on an early warning value adjusting page; and responding to the early warning value confirmation operation aiming at the operation control, reducing the standard counting early warning value based on the preset early warning value adjustment parameter to obtain an adjusted neutron counting early warning value corresponding to the area to be adjusted, and displaying the adjusted neutron counting early warning value corresponding to the area to be adjusted.
The operation control is a control for adjusting a standard count early warning value and a neutron count early warning value corresponding to each monitoring area respectively, and in an actual implementation process, the operation control can be an entity button installed on a terminal or an operation component displayed in a page, for example, the entity button can be a rotary encoder, and the operation component can be a component comprising a plurality of front-end button controls. The monitoring area selection operation refers to an operation for selecting a monitoring area that acts on an operation control. The area to be regulated is a monitoring area needing to regulate the early warning value. The early warning value adjusting page corresponding to the area to be adjusted is a page for displaying an area identifier, a standard counting early warning value, a voltage monitoring value and a neutron counting monitoring value corresponding to the area to be adjusted, and the standard counting early warning value in the early warning value adjusting page can be adjusted through early warning value adjusting operation.
The early warning value adjusting operation is an operation on an operation control for adjusting a standard counting early warning value corresponding to the monitoring area. The standard counting early warning value is a real early warning value corresponding to the monitoring area, and when the sub-data monitoring value exceeds the standard monitoring early warning value, the nuclear reactor is indicated to have accidents. The early warning value adjusting parameter is a parameter for reducing a neutron count early warning value corresponding to a monitoring area, early warning is carried out based on the neutron count early warning value, early warning can be achieved, shutdown caused by triggering accident warning is avoided, and working efficiency is improved. The early warning value confirming operation is applied to the operation control and used for confirming the standard counting early warning value determined by the early warning adjusting operation, and the standard counting early warning value and the neutron counting early warning value corresponding to the area to be adjusted are updated.
The terminal determines the area to be adjusted according to the monitoring area selection operation triggered by the operation control, and displays an early warning value adjustment page corresponding to the area to be adjusted. For example, the monitoring area selection operation may be a pressing operation acting on the rotary encoder, by which to switch to the area to be adjusted; when the operation control is an operation component displayed in the page, the operation component can comprise single-selection controls for each monitoring area, the monitoring area selection operation can be the selection operation of the single-selection control corresponding to any one monitoring area, and the selected monitoring area is determined as an area to be regulated; etc.
And the terminal responds to the early warning value adjusting operation aiming at the operation control to obtain a standard counting early warning value corresponding to the area to be adjusted, and displays the standard counting early warning value in an early warning value adjusting page. For example, the early warning value adjusting operation may be a rotation operation applied to the rotary encoder, and based on a rotation angle corresponding to the early warning value adjusting operation, an initial standard count early warning value corresponding to the to-be-adjusted area is adjusted to obtain an updated standard count early warning value corresponding to the to-be-adjusted area; when the operation control is an operation component displayed in the page, the operation component can comprise an input box control for adjusting a standard counting early warning value, and the early warning value adjusting operation can be an input operation aiming at the input box control; etc.
And the terminal responds to the early warning value confirmation operation aiming at the operation control, adjusts the standard counting early warning value based on the preset early warning value adjustment parameter to obtain a corresponding neutron counting early warning value, and displays the latest standard counting early warning value and neutron counting early warning value corresponding to the area to be adjusted on the page. For example, the early warning value adjusting parameter may be 0.7, and the product between the early warning value adjusting parameter and the standard counting early warning value is taken as a corresponding neutron counting early warning value; the early warning value adjusting parameter can be a preset neutron quantity, and the difference value between the standard counting early warning value and the early warning value adjusting parameter is used as a neutron counting early warning value; etc. In the actual implementation process, corresponding early warning value adjusting parameters can be set for each monitoring area corresponding to the target nuclear reactor according to the early warning sensitivity required by each monitoring area, and uniform early warning value adjusting parameters can also be set for each monitoring area corresponding to the target nuclear reactor.
In one embodiment, the terminal may uniformly adjust neutron count early-warning values corresponding to each monitoring area. As shown in fig. 4, the early warning value adjustment page shows neutron count monitoring values and voltage monitoring values corresponding to the channels (monitoring areas) to be adjusted respectively, and standard count early warning values (alarm thresholds) corresponding to the channels to be adjusted respectively. When the alarm threshold is 300cps, the neutron count monitoring value 913.08cps corresponding to a channel is larger than the standard count early warning value, and the abnormal alarm for the channel is triggered. The anomaly alarm includes generating a color alarm cue, for example highlighting a channel with yellow.
In the above embodiment, the input standard counting early-warning value is reduced to the corresponding neutron counting early-warning value through the preset early-warning value adjusting parameter, so that the abnormal alarm is performed when the neutron counting monitoring value is larger than the neutron counting early-warning value, thus, the early-warning is realized, the condition that the neutron counting monitoring value exceeds the standard monitoring early-warning value is avoided, and the operation safety of the nuclear reactor can be improved.
In one embodiment, a nuclear reactor status is displayed for each monitoring region, comprising:
Displaying a nuclear reactor state, a standard count early warning value, a neutron count monitoring value, a voltage monitoring value and a neutron detector identifier which are respectively corresponding to each monitoring area in a data display area; displaying the operation control in a control display area; the operation control is used for adjusting at least one of standard counting early warning value, neutron counting early warning value and alarm release.
The data display area is an area for displaying the monitoring data corresponding to each monitoring area in the target nuclear reactor. The neutron detector identification refers to a unique identification corresponding to the neutron detector and is used for distinguishing the neutron detectors corresponding to different monitoring areas respectively. The control presentation area refers to an area for presenting operation controls.
Illustratively, the terminal includes a data presentation area and a control presentation area. The terminal displays neutron detector identifications, voltage monitoring values, neutron count monitoring values, standard count early warning values, neutron count early warning values and nuclear reactor states of the neutron detectors respectively corresponding to the monitoring areas through the data display areas. And the terminal displays the operation control in the control display area.
In one embodiment, as shown in fig. 5, the terminal is a neutron display including a liquid crystal display, a buzzer, and operating controls. The liquid crystal display screen displays the monitoring data corresponding to the two channels (monitoring areas) respectively. The system comprises a main control alarm threshold (standard counting early warning value), a field alarm threshold (neutron counting early warning value), a neutron detector identifier, a voltage monitoring value and a neutron counting monitoring value, wherein the main control alarm threshold (standard counting early warning value), the field alarm threshold (neutron counting early warning value), the neutron detector identifier, the voltage monitoring value and the neutron counting monitoring value respectively correspond to the channel and the channel. In the actual implementation process, the monitoring data corresponding to the first channel and the second channel are displayed in different colors, so that the display of the monitoring data is more visual, and a worker can rapidly distinguish the monitoring data corresponding to the different channels. For example, the monitoring data corresponding to one channel is displayed in red font, and the monitoring data corresponding to two channels is displayed in blue font. If the nuclear reactor state corresponding to any channel is abnormal, the data display subarea corresponding to the channel can be highlighted. The buzzer is used for carrying out abnormal alarm when any channel is in an abnormal state. The operation control is used for adjusting the standard counting early warning value, the neutron counting early warning value and releasing the buzzer alarm. When any channel is in an abnormal state, triggering a buzzer to alarm, and highlighting the data display subarea corresponding to the channel. The staff can eliminate the buzzer alarm through operating the control, but still keep the highlighting of data show subregion to remind the staff to change the neutron count of material scene unusual. And when the neutron counts of all the channels are recovered to be normal, or the neutron count early-warning value corresponding to the channel in the abnormal state is readjusted, eliminating the highlighting of the channel in the abnormal state after the neutron count monitoring value is smaller than the neutron count early-warning value.
In the above embodiment, the terminal displays the data such as the nuclear reactor state, the standard count early warning value, the neutron count early warning value and the like corresponding to each monitoring area through the data display area, and displays the operation control through the control display area. The division of the functional areas is realized, so that the monitoring data and the nuclear reactor state corresponding to each monitoring area can be intuitively displayed, and the nuclear reactor monitoring efficiency is improved.
In one embodiment, the nuclear reactor monitoring method is applied to a neutron display including a signal conversion assembly, a display assembly, an alarm assembly, an operational control, at least two neutron detectors:
the neutron detector is used for collecting voltage monitoring values corresponding to the monitoring areas; the signal conversion component is used for converting the voltage monitoring value corresponding to the monitoring area into a corresponding neutron counting monitoring value; the display component is used for displaying the nuclear reactor state, the standard count early warning value, the neutron count monitoring value, the voltage monitoring value and the neutron detector identifier which are respectively corresponding to each monitoring area; the alarm component is used for carrying out abnormal alarm when the nuclear reactor state corresponding to the monitoring area is in an abnormal state; the operation control is used for adjusting at least one of a standard count early warning value corresponding to the monitoring area, a neutron count early warning value corresponding to the monitoring area and a release alarm.
The neutron display refers to a terminal for monitoring the state of a nuclear reactor in each monitoring area of the nuclear reactor. The neutron detector is used for detecting the number of neutrons in the monitoring area, outputting corresponding current signals, and converting the current signals into required voltage measurement signals through the precision resistor. The display component refers to a component for displaying real-time monitoring data, for example, the display component may be a display screen, a projection device or a virtual reality imaging device, and the display screen may be a liquid crystal display screen or an electronic ink display screen. The alarm component is a component for alarming in an abnormal state, and can comprise at least one of a buzzer, an audible and visual alarm, an equipment signal lamp and other alarm devices. The operation control is used for controlling the neutron display, for example, the operation control can be a touch layer covered on a display screen, a rotary encoder, a button, a track ball or a touch pad arranged on the neutron display, an external keyboard, a touch pad or a mouse and the like.
By way of example, the terminal may be a neutron display including a signal conversion component, a display component, an alarm component, an operational control, at least two neutron detectors. The neutron display firstly acquires voltage monitoring values acquired by neutron detectors corresponding to all monitoring areas respectively, and the signal conversion assembly converts the voltage monitoring values into corresponding neutron counting monitoring values. And displaying the nuclear reactor state, the standard count early warning value, the neutron count monitoring value, the voltage monitoring value and the neutron detector identifier which are respectively corresponding to each monitoring area in real time by the display assembly. When a monitoring area of which the nuclear reactor state is in an abnormal state exists, an alarm component carries out abnormal alarm on the monitoring area, and meanwhile, a data display subarea corresponding to the monitoring area can be highlighted through a display component.
In one embodiment, as shown in fig. 6, the neutron display consists of a microprocessor, a display screen, a buzzer, an operation control, a first neutron detector, a second neutron detector and a download debugging interface. The neutron detector is used for collecting voltage monitoring values in the corresponding monitoring areas. The microprocessor can be a 32-bit microcontroller, the display screen can be a liquid crystal display screen, and the download debugging interface can be an SWD download interface (Serial Wire Debug, serial line debugging).
In the above embodiment, the signal conversion component in the neutron display device converts the voltage monitoring value collected by the neutron detector into the corresponding neutron counting monitoring value, and compares the neutron counting monitoring value with the corresponding neutron counting early warning value, so that the nuclear reactor state corresponding to each monitoring area can be obtained rapidly and accurately. And the monitoring data such as neutron count monitoring values and nuclear reactor states corresponding to the monitoring areas are displayed in real time through the display assembly, so that the monitoring data are more visual, and the efficiency of nuclear reactor monitoring can be improved. When the nuclear reactor state is abnormal, the alarm assembly is used for carrying out abnormal alarm, so that staff can take countermeasures in time, the monitoring efficiency of the nuclear reactor is improved, and the safety of the nuclear reactor is ensured.
In a specific embodiment, the nuclear reactor monitoring method provided by the application can be applied to a digital neutron indicator, the digital neutron indicator is applied to a reactor factory of a nuclear power plant, and in a refueling shutdown mode, the reactor core subcritical neutron flux of a nuclear fuel loading or unloading site is continuously monitored in a digital mode. The nuclear reactor monitoring method comprises the following steps:
1. neutron counting digital display
As shown in fig. 7, the microprocessor setting, the display screen setting, the buzzer setting, the rotary encoder setting, the digital-to-analog converter setting in the digital neutron display are initialized. And acquiring a set alarm threshold value from the memory, and opening the interrupt. The digital neutron display device collects and processes sensor data of the first neutron detector and the second neutron detector, and meanwhile, the processing result is displayed on the display screen. Specifically, the digital neutron display instrument converts analog quantity signals collected by a neutron measurement probe of the neutron detector into digital quantity signals through a 12-bit AD converter (analog-digital converter) of the microcontroller, and then converts the digital quantity signals into neutron counts, and the neutron counts are displayed on an LCD (Liquid Crystal Display, liquid crystal display screen) screen.
2. Threshold alarm
As shown in fig. 7, when the neutron count exceeds the alarm threshold, a color alarm prompt for the corresponding neutron detector is triggered, and a buzzer audible alarm is triggered. And if the audible alarm confirmation signal of the buzzer is received within the preset time period, eliminating the audible alarm of the buzzer. If the buzzer audible alarm confirmation signal is not received within the preset time period and the neutron count still exceeds the alarm threshold, the color alarm prompt and the buzzer audible alarm of the corresponding channel are continuously triggered. If the buzzer sound alarm confirmation signal is not received within the preset time period and the neutron count does not exceed the alarm threshold value, resetting the alarm signal, and returning to the step of collecting and processing the sensor data of the first neutron detector and the second neutron detector.
3. Alarm threshold adjustment
The alarm threshold is obtained by a worker operating the rotary encoder, and as shown in fig. 7, the digital neutron display resets the alarm threshold based on the output signal of the rotary encoder and writes the alarm threshold into the memory. And after resetting the alarm threshold, comparing the neutron count corresponding to each channel with the current alarm threshold again to obtain the current nuclear reactor state corresponding to each channel. The digital neutron display also has a power-off memory function, and when the digital neutron display is powered on again after unexpected power-off, the alarm set value is unchanged, the alarm threshold adjustment time is saved, and the nuclear reactor monitoring efficiency can be improved.
In the above embodiment, in the conventional nuclear reactor refueling site monitoring process, a recorder is generally adopted, the voltage signal collected by the neutron detector is displayed on the recorder, the neutron count information corresponding to the refueling site cannot be directly obtained, the voltage signal is converted into the corresponding neutron count monitoring value through the digital neutron display, and then the neutron count monitoring value is compared with the alarm threshold value, so that the nuclear reactor state can be rapidly determined, and the nuclear reactor monitoring efficiency is improved. In addition, the digital neutron display instrument also has a function of independently adjusting the double-channel alarm threshold, the on-site alarm threshold can be set to be a numerical value smaller than the alarm threshold of the main control room, and the abnormal neutron counting alarm of the refueling site can be triggered before the alarm signal of the main control room appears so as to remind a refueling main pipe, increase the on-site handling control force, avoid the shutdown caused by the triggering of the alarm of the main control room and improve the working efficiency. When the material is misplaced in the material changing site, abnormal alarm can be generated in neutron counting, so that accidental critical accidents are prevented, and the operation risk of the material changing site is reduced.
It should be understood that, although the steps in the flowcharts related to the embodiments described above are sequentially shown as indicated by arrows, these steps are not necessarily sequentially performed in the order indicated by the arrows. The steps are not strictly limited to the order of execution unless explicitly recited herein, and the steps may be executed in other orders. Moreover, at least some of the steps in the flowcharts described in the above embodiments may include a plurality of steps or a plurality of stages, which are not necessarily performed at the same time, but may be performed at different times, and the order of the steps or stages is not necessarily performed sequentially, but may be performed alternately or alternately with at least some of the other steps or stages.
Based on the same inventive concept, the embodiments of the present application also provide a nuclear reactor monitoring apparatus for implementing the above-mentioned related nuclear reactor monitoring method. The implementation of the solution provided by the device is similar to that described in the above method, so the specific limitations in one or more embodiments of the nuclear reactor monitoring device provided below may be referred to above for the limitations of the nuclear reactor monitoring method, and will not be repeated here.
In one embodiment, as shown in FIG. 8, a nuclear reactor monitoring device is provided, comprising: a voltage monitor value acquisition module 802, a neutron count value conversion module 804, a nuclear reactor status determination module 806, and a nuclear reactor status display module 808, wherein:
a voltage monitoring value obtaining module 802, configured to obtain voltage monitoring values corresponding to at least two monitoring areas of the target nuclear reactor respectively; the voltage monitoring value is acquired by neutron detectors in the monitored area.
The neutron count value conversion module 804 is configured to convert the voltage monitoring value collected by the neutron detector into a neutron count monitoring value based on the monitoring range information corresponding to the neutron detector, so as to obtain neutron count monitoring values corresponding to each monitoring area respectively.
The nuclear reactor state determining module 806 is configured to compare the neutron count monitoring value and the neutron count early warning value corresponding to the same monitoring area, and obtain the nuclear reactor states corresponding to the monitoring areas respectively.
The nuclear reactor state display module 808 is configured to display a nuclear reactor state corresponding to each of the monitoring areas.
In one embodiment, neutron count value conversion module 804 is further configured to:
aiming at the neutron detector in the current monitoring area, converting a voltage monitoring value corresponding to the current monitoring area into a reference voltage value based on a voltage monitoring range in monitoring range information corresponding to the neutron detector; the reference voltage value is used for indicating the position of the voltage monitoring value corresponding to the current monitoring area in the voltage monitoring range; and mapping the reference voltage value into a neutron count monitoring value based on the neutron count monitoring range in the monitoring range information, and obtaining the neutron count monitoring value corresponding to the current monitoring area.
In one embodiment, the nuclear reactor status determination module 806 is further configured to:
determining a nuclear reactor state corresponding to a monitoring area with a neutron counting monitoring value larger than a neutron counting early warning value as an abnormal state, and determining a nuclear reactor state corresponding to a monitoring area with a neutron counting monitoring value smaller than or equal to the neutron counting early warning value as a normal state to obtain a nuclear reactor state corresponding to each monitoring area respectively; the nuclear reactor status is used for indicating an abnormality alarm for the monitoring area.
In one embodiment, the nuclear reactor status display module 808 is further configured to:
displaying a nuclear reactor state, a standard count early warning value, a neutron count monitoring value, a voltage monitoring value and a neutron detector identifier which are respectively corresponding to each monitoring area in a data display area;
displaying the operation control in a control display area; the operation control is used for adjusting at least one of standard counting early warning value, neutron counting early warning value and alarm release.
In one embodiment, as shown in fig. 9, the nuclear reactor monitoring device further comprises:
the early warning value adjusting module 902 is configured to determine an area to be adjusted in each monitoring area in response to a monitoring area selection operation for the operation control, and display an early warning value adjusting page corresponding to the area to be adjusted; responding to the early warning value adjusting operation aiming at the operation control, and displaying a standard counting early warning value corresponding to the area to be adjusted on an early warning value adjusting page; and responding to the early warning value confirmation operation aiming at the operation control, reducing the standard counting early warning value based on the preset early warning value adjustment parameter to obtain an adjusted neutron counting early warning value corresponding to the area to be adjusted, and displaying the adjusted neutron counting early warning value corresponding to the area to be adjusted.
In one embodiment, the nuclear reactor monitoring method is applied to a neutron display including a signal conversion assembly, a display assembly, an alarm assembly, an operational control, at least two neutron detectors:
the neutron detector is used for collecting voltage monitoring values corresponding to the monitoring areas; the signal conversion component is used for converting the voltage monitoring value corresponding to the monitoring area into a corresponding neutron counting monitoring value; the display component is used for displaying the nuclear reactor state, the standard count early warning value, the neutron count monitoring value, the voltage monitoring value and the neutron detector identifier which are respectively corresponding to each monitoring area; the alarm component is used for carrying out abnormal alarm when the nuclear reactor state corresponding to the monitoring area is in an abnormal state; the operation control is used for adjusting at least one of a standard count early warning value corresponding to the monitoring area, a neutron count early warning value corresponding to the monitoring area and a release alarm.
According to the nuclear reactor monitoring device, according to the monitoring range information corresponding to the neutron detector, the voltage monitoring values corresponding to the monitoring areas are converted into the corresponding neutron counting monitoring values, and then the nuclear reactor states corresponding to the monitoring areas can be rapidly and accurately determined according to the neutron counting monitoring values and the neutron counting early warning values corresponding to the same monitoring area, so that the nuclear reactor monitoring efficiency is improved.
The various modules in the nuclear reactor monitoring device described above may be implemented in whole or in part by software, hardware, and combinations thereof. The above modules may be embedded in hardware or may be independent of a processor in the computer device, or may be stored in software in a memory in the computer device, so that the processor may call and execute operations corresponding to the above modules.
In one embodiment, a computer device is provided, which may be a terminal, and an internal structure diagram thereof may be as shown in fig. 10. The computer device includes a processor, a memory, an input/output interface, a communication interface, a display unit, and an input means. The processor, the memory and the input/output interface are connected through a system bus, and the communication interface, the display unit and the input device are connected to the system bus through the input/output interface. Wherein the processor of the computer device is configured to provide computing and control capabilities. The memory of the computer device includes a non-volatile storage medium and an internal memory. The non-volatile storage medium stores an operating system and a computer program. The internal memory provides an environment for the operation of the operating system and computer programs in the non-volatile storage media. The input/output interface of the computer device is used to exchange information between the processor and the external device. The communication interface of the computer device is used for carrying out wired or wireless communication with an external terminal, and the wireless mode can be realized through WIFI, a mobile cellular network, NFC (near field communication) or other technologies. The computer program when executed by a processor implements a nuclear reactor monitoring method. The display unit of the computer device is used for forming a visual picture, and can be a display screen, a projection device or a virtual reality imaging device. The display screen can be a liquid crystal display screen or an electronic ink display screen, and the input device of the computer equipment can be a touch layer covered on the display screen, can also be a key, a track ball or a touch pad arranged on the shell of the computer equipment, and can also be an external keyboard, a touch pad or a mouse and the like.
It will be appreciated by those skilled in the art that the structure shown in fig. 10 is merely a block diagram of some of the structures associated with the present application and is not limiting of the computer device to which the present application may be applied, and that a particular computer device may include more or fewer components than shown, or may combine certain components, or have a different arrangement of components.
In one embodiment, a computer device is provided, comprising a memory and a processor, the memory having stored therein a computer program, the processor implementing the steps of the method embodiments described above when the computer program is executed.
In one embodiment, a computer-readable storage medium is provided, on which a computer program is stored which, when executed by a processor, implements the steps of the method embodiments described above.
In one embodiment, a computer program product or computer program is provided that includes computer instructions stored in a computer readable storage medium. The processor of the computer device reads the computer instructions from the computer-readable storage medium, and the processor executes the computer instructions, so that the computer device performs the steps in the above-described method embodiments.
It should be noted that, the user information (including, but not limited to, user equipment information, user personal information, etc.) and the data (including, but not limited to, data for analysis, stored data, presented data, etc.) referred to in the present application are information and data authorized by the user or sufficiently authorized by each party, and the collection, use and processing of the related data are required to comply with the related laws and regulations and standards of the related countries and regions.
Those skilled in the art will appreciate that implementing all or part of the above described methods may be accomplished by way of a computer program stored on a non-transitory computer readable storage medium, which when executed, may comprise the steps of the embodiments of the methods described above. Any reference to memory, database, or other medium used in the various embodiments provided herein may include at least one of non-volatile and volatile memory. The nonvolatile Memory may include Read-Only Memory (ROM), magnetic tape, floppy disk, flash Memory, optical Memory, high density embedded nonvolatile Memory, resistive random access Memory (ReRAM), magnetic random access Memory (Magnetoresistive Random Access Memory, MRAM), ferroelectric Memory (Ferroelectric Random Access Memory, FRAM), phase change Memory (Phase Change Memory, PCM), graphene Memory, and the like. Volatile memory can include random access memory (Random Access Memory, RAM) or external cache memory, and the like. By way of illustration, and not limitation, RAM can be in the form of a variety of forms, such as static random access memory (Static Random Access Memory, SRAM) or dynamic random access memory (Dynamic Random Access Memory, DRAM), and the like. The databases referred to in the various embodiments provided herein may include at least one of relational databases and non-relational databases. The non-relational database may include, but is not limited to, a blockchain-based distributed database, and the like. The processors referred to in the embodiments provided herein may be general purpose processors, central processing units, graphics processors, digital signal processors, programmable logic units, quantum computing-based data processing logic units, etc., without being limited thereto.
The technical features of the above embodiments may be arbitrarily combined, and all possible combinations of the technical features in the above embodiments are not described for brevity of description, however, as long as there is no contradiction between the combinations of the technical features, they should be considered as the scope of the description.
The above examples only represent a few embodiments of the present application, which are described in more detail and are not to be construed as limiting the scope of the present application. It should be noted that it would be apparent to those skilled in the art that various modifications and improvements could be made without departing from the spirit of the present application, which would be within the scope of the present application. Accordingly, the scope of protection of the present application shall be subject to the appended claims.
Claims (10)
1. A method of nuclear reactor monitoring, the method comprising:
acquiring voltage monitoring values respectively corresponding to at least two monitoring areas of a target nuclear reactor; the voltage monitoring value is acquired by a neutron detector in the monitoring area;
converting the voltage monitoring value acquired by the neutron detector into a neutron counting monitoring value based on the monitoring range information corresponding to the neutron detector, and obtaining neutron counting monitoring values corresponding to all monitoring areas respectively;
Comparing neutron count monitoring values and neutron count early warning values corresponding to the same monitoring area to respectively obtain nuclear reactor states corresponding to the monitoring areas;
and displaying the nuclear reactor states respectively corresponding to the monitoring areas.
2. The method according to claim 1, wherein the converting the voltage monitoring value collected by the neutron detector into the neutron count monitoring value based on the monitoring range information corresponding to the neutron detector to obtain the neutron count monitoring value corresponding to each monitoring area, includes:
aiming at a neutron detector in a current monitoring area, converting a voltage monitoring value corresponding to the current monitoring area into a reference voltage value based on a voltage monitoring range in monitoring range information corresponding to the neutron detector; the reference voltage value is used for indicating the position of the voltage monitoring value corresponding to the current monitoring area in the voltage monitoring range;
and mapping the reference voltage value into a neutron count monitoring value based on the neutron count monitoring range in the monitoring range information to obtain the neutron count monitoring value corresponding to the current monitoring area.
3. The method of claim 1, wherein comparing neutron count monitoring values and neutron count pre-warning values corresponding to the same monitoring region to obtain nuclear reactor states corresponding to the respective monitoring regions, respectively, comprises:
Determining a nuclear reactor state corresponding to a monitoring area with a neutron counting monitoring value larger than a neutron counting early warning value as an abnormal state, and determining a nuclear reactor state corresponding to a monitoring area with a neutron counting monitoring value smaller than or equal to the neutron counting early warning value as a normal state to obtain the nuclear reactor states respectively corresponding to the monitoring areas; the nuclear reactor status is used for indicating to perform abnormal alarm aiming at the monitoring area.
4. The method according to claim 1, wherein the method further comprises:
responding to monitoring area selection operation aiming at an operation control, determining areas to be regulated in the monitoring areas, and displaying an early warning value regulating page corresponding to the areas to be regulated;
responding to the early warning value adjusting operation aiming at the operation control, and displaying a standard counting early warning value corresponding to the area to be adjusted on the early warning value adjusting page;
and responding to the early warning value confirmation operation aiming at the operation control, reducing the standard counting early warning value based on a preset early warning value adjustment parameter to obtain an adjusted neutron counting early warning value corresponding to the area to be adjusted, and displaying the adjusted neutron counting early warning value corresponding to the area to be adjusted.
5. The method of claim 1, wherein said displaying the respective corresponding nuclear reactor status for each of the monitored areas comprises:
displaying the nuclear reactor state, the standard counting early warning value, the neutron counting monitoring value, the voltage monitoring value and the neutron detector identifier which are respectively corresponding to each monitoring area in a data display area;
displaying the operation control in a control display area; the operation control is used for adjusting at least one of standard count early warning value, neutron count early warning value and alarm release.
6. The method of claim 1, wherein the method is applied to a neutron display including a signal conversion assembly, a display assembly, an alarm assembly, an operational control, at least two neutron detectors:
the neutron detector is used for collecting voltage monitoring values corresponding to the monitoring areas;
the signal conversion component is used for converting the voltage monitoring value corresponding to the monitoring area into a corresponding neutron counting monitoring value;
the display component is used for displaying the nuclear reactor state, the standard counting early warning value, the neutron counting monitoring value, the voltage monitoring value and the neutron detector identifier which are respectively corresponding to the monitoring areas;
The alarm component is used for carrying out abnormal alarm when the nuclear reactor state corresponding to the monitoring area is in an abnormal state;
the operation control is used for adjusting at least one of a standard count early warning value corresponding to the monitoring area, a neutron count early warning value corresponding to the monitoring area and releasing the alarm.
7. A nuclear reactor monitoring device, the device comprising:
the voltage monitoring value acquisition module is used for acquiring voltage monitoring values corresponding to at least two monitoring areas of the target nuclear reactor respectively; the voltage monitoring value is acquired by a neutron detector in the monitoring area;
the neutron count value conversion module is used for converting the voltage monitoring value acquired by the neutron detector into a neutron count monitoring value based on the monitoring range information corresponding to the neutron detector, so as to obtain neutron count monitoring values corresponding to all monitoring areas respectively;
the nuclear reactor state determining module is used for comparing the neutron count monitoring value and the neutron count early warning value corresponding to the same monitoring area to respectively obtain the nuclear reactor states corresponding to the monitoring areas;
and the nuclear reactor state display module is used for displaying the nuclear reactor states respectively corresponding to the monitoring areas.
8. A computer device comprising a memory and a processor, the memory storing a computer program, characterized in that the processor implements the steps of the method of any of claims 1 to 6 when the computer program is executed.
9. A computer readable storage medium, on which a computer program is stored, characterized in that the computer program, when being executed by a processor, implements the steps of the method of any of claims 1 to 6.
10. A computer program product comprising a computer program, characterized in that the computer program, when being executed by a processor, implements the steps of the method of any of claims 1 to 6.
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