CN115359934A - Intelligent monitoring method and system for reactor internals of nuclear power station reactor - Google Patents
Intelligent monitoring method and system for reactor internals of nuclear power station reactor Download PDFInfo
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- CN115359934A CN115359934A CN202211138334.6A CN202211138334A CN115359934A CN 115359934 A CN115359934 A CN 115359934A CN 202211138334 A CN202211138334 A CN 202211138334A CN 115359934 A CN115359934 A CN 115359934A
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- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The invention provides an intelligent monitoring method and system for a reactor internals of a nuclear power station, relating to the technical field of intelligent monitoring of the nuclear power station. The invention does not need to add a monitoring hardware sensor. The safety and the reliability of the operation of the reactor internal components can be improved.
Description
Technical Field
The invention relates to the technical field of intelligent monitoring of nuclear power stations, in particular to an intelligent monitoring method and system for reactor internals of a nuclear power station reactor.
Background
The statements in this section merely provide background information related to the present disclosure and may not constitute prior art.
The reactor internals are important equipment of a nuclear power plant and are composed of a core support structure and internal structures. Core support structure refers to a structure that directly supports or constrains the core (fuel assemblies and related assemblies) within the reactor pressure vessel. Internal structure refers to structure within the reactor pressure vessel other than the core support structure, fuel assemblies and related assemblies, and core instrumentation thimble assemblies. These structures are mounted within the reactor pressure vessel, receive and support the core, and function in combination with the reactor pressure vessel, control rod drive mechanisms, fuel assemblies and related components.
The safety and the economical efficiency of the safe and reliable operation of the reactor internals of the nuclear power plant have important influence. According to the failure mode analysis of the reactor internals, the main failures are represented by environmental fatigue failure of the internals parts such as hanging baskets, coaming assemblies and the like, high-cycle fatigue failure of secondary supporting structures and the like, stress relaxation of fasteners, abrasion of guide cylinders and compression elastic rings, loosening and falling of the internals parts, foreign matters and the like. Most of the existing monitoring of the reactor internals is to set a plurality of newly-added sensors for acquisition and monitoring, but if the monitoring of a plurality of reactors is to monitor one of the newly-added sensors, the additional time and workload of monitoring are greatly increased, and the monitoring efficiency is not high.
Disclosure of Invention
The invention provides an intelligent monitoring method and system for nuclear power station reactor internals for solving the problems, and provides a more comprehensive intelligent monitoring system for solving the problem that only single content is monitored in the prior art.
According to some embodiments, the invention adopts the following technical scheme:
the intelligent monitoring system for the reactor internals of the nuclear power station comprises a transient identification module, an equipment fastener stress relaxation monitoring module and an equipment flow field digital twin module, wherein the transient identification module, the equipment fastener stress relaxation monitoring module and the equipment flow field digital twin module are connected with a display module, the display module is used for switching inlets of all monitoring modules, and each module is manually input and controlled to complete corresponding monitoring calculation.
The system further comprises an overall operation overview module of the equipment, wherein the overall operation overview module of the equipment is an overview of monitoring data of the stack components, and the data is imported from each monitoring module.
The file management system further comprises a data and file management module, wherein the data and file management module is used for summarizing files and parameters of the in-pile component during design, manufacture and operation.
Further, the temperature, pressure and flow data of the primary side inlet and outlet required in the equipment flow field digital twin module are from the existing database, and the flow field distribution result and the related flow field data of the in-pile component are calculated according to the input data.
Furthermore, the equipment flow field digital twin module is connected with the equipment flow induced vibration monitoring module, flow speed data required by the equipment flow induced vibration monitoring module is obtained by flow field data output by the equipment flow field digital twin module through calculation, and relevant data of the flow induced vibration of the components in the reactor are calculated through input data.
Furthermore, the fast neutron fluence, the corrected lead factor and the accumulated irradiation dose required by the fastener stress relaxation monitoring module are obtained by the result of each time of extracting the irradiation monitoring tube for testing and the calculation result based on the test.
Furthermore, still include guide cylinder wearing and tearing monitoring module and compress tightly elastic ring wearing and tearing monitoring module, required guide cylinder wearing and tearing volume, wearing and tearing position offset data obtain data and input when by overhaul at every turn in the guide cylinder wearing and tearing monitoring module.
Furthermore, the data of the abrasion loss and the abrasion position offset of the compression elastic ring required by the compression elastic ring abrasion monitoring module are obtained and input during each overhaul.
According to some embodiments, the invention adopts the following technical scheme:
an intelligent monitoring method for a reactor internals of a nuclear power station reactor comprises the steps of entering each monitoring module through an equipment overall operation overview module, selecting input fluency through a selection frame when equipment flow induced vibration calculation is carried out, selecting a current flow field or a flow field obtained by calculation at any time, selecting a component needing to be calculated through the selection frame, clicking a button to start calculation, and generating a flow induced vibration predicted value and an allowable value.
Furthermore, in the device transient recognition module, an operation transient list and historical transient statistics can be selected through a selection box, and transient analysis results, different systems, screening conditions, transient categories, names and occurrence times are displayed and counted.
Compared with the prior art, the invention has the following beneficial effects:
the invention can be used as a set of integrated in-pile component intelligent monitoring software for thermal performance monitoring, flow-induced vibration monitoring, fatigue monitoring, loose part monitoring, stress relaxation monitoring, wear evaluation and transient recognition, can be used for the full life cycle management of in-pile components, and is not added with new sensors in the installation process of the system, so that the installation is simpler and more convenient. Meanwhile, the system can monitor data such as the wear condition which cannot be monitored, the flow field distribution condition and the like, and predict the stress relaxation condition of the fastener, so that the time required by maintenance of the in-reactor components is greatly reduced, and the economic benefit of the nuclear power station is improved.
Drawings
The accompanying drawings, which are incorporated in and constitute a part of this specification, are included to provide a further understanding of the invention, and are incorporated in and constitute a part of this specification, illustrate exemplary embodiments of the invention and together with the description serve to explain the invention and not to limit the invention.
FIG. 1 is an overview of the overall operation of a reactor internals arrangement;
FIG. 2 is a digital twinning module of a flow field of a component in a reactor;
FIG. 3 is a flow induced vibration monitoring module for the reactor internals;
FIG. 4 is a reactor internals loose part monitoring module;
FIG. 5 is a fatigue damage monitoring module for the reactor internals;
FIG. 6 is a reactor internals fastener stress relaxation monitoring module;
FIG. 7 is a reactor internals wear monitoring module;
FIG. 8 is a reactor internals transient identification module;
FIG. 9 is a reactor internals data and file management module;
the specific implementation mode is as follows:
the invention is further described with reference to the following figures and examples.
It is to be understood that the following detailed description is exemplary and is intended to provide further explanation of the invention as claimed. Unless defined otherwise, all technical and scientific terms used herein have the same meaning as commonly understood by one of ordinary skill in the art to which this invention belongs.
It is noted that the terminology used herein is for the purpose of describing particular embodiments only and is not intended to be limiting of exemplary embodiments according to the invention. As used herein, the singular forms "a", "an" and "the" are intended to include the plural forms as well, and it should be understood that when the terms "comprises" and/or "comprising" are used in this specification, they specify the presence of stated features, steps, operations, devices, components, and/or combinations thereof, unless the context clearly indicates otherwise.
Example 1
The invention provides an intelligent monitoring system for a reactor internals of a nuclear power station reactor, which comprises an equipment general operation condition overview module, an equipment flow field digital twin module, an equipment flow induced vibration monitoring module, an equipment loosening monitoring module, an equipment fatigue damage monitoring module, an equipment fastener stress relaxation monitoring module, an equipment wear monitoring module, a transient recognition module and a data and file management module.
The monitoring modules are connected with a display module, the display module is used for displaying a selection interface, entering the monitoring modules, switching the inlets of the monitoring modules and manually inputting and controlling the monitoring modules to complete corresponding monitoring calculation.
The overall operation overview module of the equipment is an overview of monitoring data of the stack components, and the data is imported from each monitoring module.
The data and file management module is used for summarizing various files and parameters of the in-pile components during design, manufacture and operation.
The temperature, pressure and flow data of a primary side inlet and outlet required in the equipment flow field digital twin module are from an existing database, the flow field distribution result and related flow field data of the in-pile component are calculated according to the input data, the existing database is in the existing RCS system, additional data are obtained without newly adding measuring points, and the flow field distribution result and the related flow field data of the in-pile component are calculated according to the input data.
In the equipment loose part monitoring module, needed loose part signals at various positions are led in by a loose part monitoring system installed in the nuclear power station.
In the equipment fatigue damage monitoring module, required fatigue accumulation factors of all parts are imported by an installed fatigue monitoring system of the nuclear power station.
The loose part monitoring system and the fatigue monitoring system are a set of software and hardware systems already installed on a reactor body of the nuclear power station and are used for monitoring a loose part impact event and a fatigue transient event occurring in a Reactor Coolant System (RCS).
The equipment flow field digital twin module is connected with the equipment flow induced vibration monitoring module, flow speed data required by the equipment flow induced vibration monitoring module is obtained by flow field data output by the equipment flow field digital twin module through calculation, and relevant data of flow induced vibration of the in-pile member is calculated through input data.
The fast neutron fluence, the corrected lead factor and the accumulated irradiation dose required in the fastener stress relaxation monitoring module are obtained by the result of each time of extracting the irradiation monitoring tube for testing and the calculation result based on the test.
Still include guide cylinder wearing and tearing monitoring module and compress tightly elastic ring wearing and tearing monitoring module, required guide cylinder wearing and tearing volume, wearing and tearing position offset data obtain data and input when overhauing by every turn in the guide cylinder wearing and tearing monitoring module. The data of the abrasion loss and the abrasion position offset of the compression elastic ring required by the compression elastic ring abrasion monitoring module are obtained and input during each overhaul.
And (3) calculating the prediction analysis of the related flow-induced vibration and stress relaxation by using the existing monitoring data and the data obtained by regular in-service inspection.
The device has the function of displaying the overview of the whole running condition of the device, collects and displays data including but not limited to pressure and temperature real-time change curves of inlet and outlet connecting pipes in real time, and monitors and alarms the real-time data of a main monitoring module. The data and file management module can call data information of the reactor internals in the design, manufacturing and operation stages, including design drawings, design specifications, maintenance manuals and the like in the design stages, completion drawings, completion reports, maintenance manuals and the like in the manufacturing stages, operation rules, in-service inspection reports and the like in the operation stages.
As an example, the monitoring process of the reactor internals of the present invention comprises:
step 1: the method comprises the steps of entering each monitoring module through an equipment overall operation overview module, switching groups/plant sites/units, displaying the name of the current unit, displaying the temperature and flow real-time change curves of an inlet and an outlet, monitoring and alarming real-time data of a main monitoring module, and sending an alarm and alarm information when abnormal conditions occur.
Step 2: in the equipment flow field digital twin module, flow field calculation can be carried out through a button, and calculation results of flow velocity, temperature and the like of a loop flow field are obtained by utilizing flow field data and calculation methods of vortex shedding and turbulent flow excitation; and selecting corresponding physical quantities such as flow speed and temperature in a selection frame, and displaying two physical quantity cloud pictures corresponding to vertical sections. And selecting time and position in the selection frame, and generating a random corresponding physical quantity cloud picture after selecting physical quantity in the selection frame.
And step 3: in the equipment flow induced vibration monitoring module, an input flow field can be selected through a selection frame, a current flow field or a flow field obtained by calculation at any other time can be selected, components needing to be calculated, such as a hanging basket, a guide cylinder, a secondary supporting component and the like, are selected through the selection frame, a button is clicked to start calculation, a component prediction node schematic diagram is displayed, a flow induced vibration prediction value and an allowable value are generated, and a component prediction alarm area is displayed.
And 4, step 4: in the equipment loose part monitoring module, selecting a positioning result and a quality estimation result of a loose part alarm event, displaying a stack body view, marking a loose part sensor position, and displaying a sensor measuring point position triggered by alarm as red after the loose part alarm event occurs; and selecting an original waveform at a selection box, positioning, analyzing and estimating the quality to obtain a corresponding analysis result, and then displaying a release alarm event history list.
And 5: in the equipment fatigue damage monitoring module, fatigue limit positions of equipment and pipelines are screened in a water environment, then fatigue damage phenomena of important equipment and pipelines of a power plant are monitored, and fatigue accumulation factor calculation under transient load is carried out in real time by a fatigue accumulation factor calculation method based on a transfer function. The software displays the view of the in-pile member, marks the fatigue monitoring point part in the view, displays the real-time fatigue damage factor values of the monitoring point, including information such as the sequence number, the monitoring point, the description, the CUF (ASME standard fatigue damage factor), the EAF (environmental impact fatigue damage factor), the calculation time, the state and the like, and monitors and alarms the fatigue factor. After selecting the corresponding location and time at the selection box, a historical fatigue damage factor curve may be displayed in the area.
Further, in the equipment fastener stress relaxation monitoring module, by collecting the stress relaxation coefficients of various RVI materials, under the condition that the neutron fluence and the pretightening force are known, the stress relaxation condition of the equipment fastener caused by irradiation can be estimated. Selecting a cumulative stress relaxation list of the fastener, and displaying a view of the internals and the position of the fastener; by selecting a single fastener and starting time at the selection box, a fastener stress relaxation history may be obtained.
In the equipment wear monitoring module, the time (next overhaul or end of life) can be selected through a selection box; displaying a guide cylinder abrasion condition cloud picture; the number of guide cylinders displaying different abrasion amounts; inputting the row number and the column number of the guide cylinder to be checked at the text box, and displaying the wear prediction condition of the guide cylinder; clicking a button to derive a guide cylinder abrasion condition related report; the highly averaged measurements of the compression spring ring during the past overhaul are then displayed.
In the device transient recognition module, transient management, that is, real-time monitoring of the transient and statistical analysis of the transient, is required. The transient events are automatically recorded through a real-time monitoring system of the nuclear power plant and a trained artificial neural network transient recognition algorithm, and are classified into each type of transient state. The software can select an operation transient list and historical transient statistics through a selection box; displaying the transient analysis result and displaying different systems and screening conditions; displaying transient category, name and occurrence frequency, and displaying transient category statistics; and finally displaying the transient type statistics.
In the data and file management module, various parameters of the in-pile component in the stages of design, manufacture and operation can be checked through buttons, and corresponding parameter values and tables are displayed; design atlas, design instruction manual and maintenance manual are used in the design stage, completion drawing, completion report and maintenance manual are used in the manufacturing stage, operation regulation and in-service inspection report are used in the operation stage, and relevant files can be called and viewed by clicking corresponding buttons.
Example 2
An embodiment of the present invention provides an intelligent monitoring method for a reactor internals of a nuclear power plant, based on the monitoring system described in embodiment 1, as shown in fig. 1, the intelligent monitoring method includes an equipment overall operation condition overview module, an equipment flow field digital twin module, an equipment flow induced vibration monitoring module, an equipment loosening member monitoring module, an equipment fatigue damage monitoring module, an equipment fastener stress relaxation monitoring module, an equipment wear monitoring module, a transient recognition module, and a data and file management module.
As shown in fig. 1-9, each specific monitoring module can enter through the (10) area, the group/plant site/unit can be switched in the (11) area, the current unit name is displayed, the real-time change curves of the temperature and the flow of the inlet and the outlet can be displayed in the (12) area, the real-time data of the main monitoring module is monitored and alarmed in the (13) area, and when an abnormal condition occurs, alarm information appears in the (14) area.
In the equipment flow field digital twin module, the flow field calculation can be carried out through a button (20); the corresponding physical quantities, such as flow rate and temperature, are selected in a selection frame (21), and two physical quantity clouds corresponding to vertical sections perpendicular to each other can be displayed in an area (22). After the selection frame (23) selects time, the selection frame (24) selects position, and the selection frames (25) and (26) select physical quantity, any corresponding physical quantity cloud pictures can be generated at the area (27).
In the equipment flow-induced vibration monitoring module, an input flow field can be selected through a selection frame (30), the current flow field or the flow field obtained by any other calculation at any time can be selected, components needing to be calculated, such as a hanging basket, a guide cylinder, a secondary supporting component and the like, are selected through a selection frame (33), a button (31) is clicked to start calculation, a component prediction node schematic diagram is displayed in an area (32), a flow-induced vibration prediction value and an allowable value are generated in an area (34), and a component prediction alarm area is displayed in an area (35).
In the equipment loose part monitoring module, selecting a positioning result and a quality estimation result of a loose part alarm event at an area (40), displaying a stack body view at an area (42), marking a loose part sensor position, and displaying a sensor measuring point position triggered by alarm as red after a rear loose part alarm event occurs; selecting an original waveform at a selection frame (41), and performing positioning analysis and quality estimation to obtain a corresponding analysis result; a trip alarm event history list is displayed at area (43).
In the equipment fatigue damage monitoring module, a view of the in-pile component is displayed in a region (50), a fatigue monitoring point part is identified in the view, real-time fatigue damage factor values of the monitoring point are displayed in a region (51), the real-time fatigue damage factor values comprise information such as a sequence number, a monitoring point, description, a CUF (ASME standard fatigue damage factor), an EAF (environmental impact fatigue damage factor), calculation time and state, and the fatigue factor is monitored and alarmed in a region (53). After selecting the corresponding location and time at the selection box (52), a historical fatigue damage factor curve may be displayed in the area (54).
In an equipment fastener stress relaxation monitoring module, selecting a list of cumulative stress relaxations of fasteners at region (60), displaying a internals view and fastener locations at region (61); by selecting a single fastener and start time at a selection box (62), a fastener stress relaxation history can be obtained at region (63).
In the equipment wear monitoring module, the time (next overhaul or end of life) can be selected by a selection box (70); a cloud picture of guide cylinder abrasion is displayed in an area (72); the number of guide cylinders displaying different amounts of wear in the area (70); inputting the row number and the column number of a guide cylinder to be checked at a text box (71), and displaying the predicted wear condition of the guide cylinder; clicking on the button (73) can lead out a report related to the abrasion condition of the guide cylinder; the average measurement of the height of the compression spring ring during a past overhaul is shown in area (74).
In the device transient identification module, a list of operating transients and historical transient statistics may be selected via a selection block (80); displaying the transient analysis results in a region (81); displaying different systems and screening conditions in an area (82); displaying the transient category, name and number of occurrences in a region (82); displaying transient category statistics in a region (84); transient type statistics are displayed in region (85).
In the data and file management module, various parameters of the in-pile component in the stages of design, manufacture and operation can be viewed through a button (90), and corresponding parameter values and tables are displayed in an area (91); files related to the internals at each stage are recorded in the region (92), a design atlas, a design instruction book and a maintenance manual are recorded in the design stage, an as-built drawing, a completion report and a maintenance manual are recorded in the manufacturing stage, an operation rule and an in-service inspection report are recorded in the operation stage, and the corresponding buttons are clicked to call the related files for viewing.
The present invention is described with reference to flowchart illustrations and/or block diagrams of methods, apparatus (systems), and computer program products according to embodiments of the invention. It will be understood that each flow and/or block of the flow diagrams and/or block diagrams, and combinations of flows and/or blocks in the flow diagrams and/or block diagrams, can be implemented by computer program instructions. These computer program instructions may be provided to a processor of a general purpose computer, special purpose computer, embedded processor, or other programmable data processing apparatus to produce a machine, such that the instructions, which execute via the processor of the computer or other programmable data processing apparatus, create means for implementing the functions specified in the flowchart flow or flows and/or block diagram block or blocks.
These computer program instructions may also be loaded onto a computer or other programmable data processing apparatus to cause a series of operational steps to be performed on the computer or other programmable apparatus to produce a computer implemented process such that the instructions which execute on the computer or other programmable apparatus provide steps for implementing the functions specified in the flowchart flow or flows and/or block diagram block or blocks.
Although the embodiments of the present invention have been described with reference to the accompanying drawings, it is not intended to limit the scope of the present invention, and it should be understood by those skilled in the art that various modifications and variations can be made without inventive efforts by those skilled in the art based on the technical solution of the present invention.
Claims (10)
1. The intelligent monitoring system for the reactor internals of the nuclear power station is characterized by comprising a transient recognition module, an equipment fastener stress relaxation monitoring module and an equipment flow field digital twin module, wherein the transient recognition module, the equipment fastener stress relaxation monitoring module and the equipment flow field digital twin module are connected with a display module, the display module is used for switching inlets of all monitoring modules, and each module is manually input and controlled to complete corresponding monitoring calculation.
2. The system of claim 1, further comprising an equipment overview module, wherein the equipment overview module is an overview of the monitoring data of the reactor components, and wherein the data is imported from each monitoring module.
3. The system of claim 1, further comprising a data and file management module, wherein the data and file management module is configured to collect files and parameters of the internals during design, manufacture, and operation.
4. The system of claim 1, wherein the primary inlet/outlet temperature, pressure, and flow data required in the plant flow field digital twin module are obtained from an existing database, and the distribution results of the flow field of the reactor internals and the related flow field data are calculated based on the input data.
5. The intelligent monitoring system for the nuclear power plant reactor internals according to claim 2, wherein the equipment flow field digital twin module is connected to the equipment flow induced vibration monitoring module, the flow rate data required by the equipment flow field digital twin module is obtained from the flow field data output by the equipment flow field digital twin module through calculation, and the data related to the flow induced vibration of the internals is calculated through input data.
6. The intelligent monitoring system for the reactor internals of the nuclear power plant as recited in claim 1, wherein the fast neutron fluence, the corrected lead factor and the accumulated irradiation dose required by the fastener stress relaxation monitoring module are obtained from the results of the test performed by extracting the irradiation monitoring tube every time and the calculation results based on the test.
7. The system according to claim 1, further comprising a guide cylinder wear monitoring module and a compression elastic ring wear monitoring module, wherein the guide cylinder wear amount and wear position offset data required in the guide cylinder wear monitoring module are obtained and input from each overhaul.
8. The system as claimed in claim 7, wherein the data of the abrasion amount and the abrasion position offset of the elastic compression ring required by the elastic compression ring abrasion monitoring module is obtained and input from each overhaul.
9. An intelligent monitoring method for a reactor internals of a nuclear power station is characterized in that an equipment overall operation overview module enters each monitoring module, when equipment flow induced vibration calculation is carried out, smoothness of input is selected through a selection frame, a current flow field or a flow field obtained by calculation at any time is selected, components needing to be calculated are selected through the selection frame, a button is clicked to start calculation, and a flow induced vibration predicted value and a permissible value are generated.
10. The method as claimed in claim 9, wherein in the equipment transient recognition module, the operating transient list and historical transient statistics can be selected by the selection box, and the transient analysis result, different systems and screening conditions, and the transient category, name and occurrence number are displayed and counted.
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| CN202211138334.6A CN115359934A (en) | 2022-09-19 | 2022-09-19 | Intelligent monitoring method and system for reactor internals of nuclear power station reactor |
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| CN202211138334.6A CN115359934A (en) | 2022-09-19 | 2022-09-19 | Intelligent monitoring method and system for reactor internals of nuclear power station reactor |
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Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. |