CN114398751B - Combined monitoring platform of nuclear turbine - Google Patents
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- CN114398751B CN114398751B CN202111456675.3A CN202111456675A CN114398751B CN 114398751 B CN114398751 B CN 114398751B CN 202111456675 A CN202111456675 A CN 202111456675A CN 114398751 B CN114398751 B CN 114398751B
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Abstract
The invention provides a combined monitoring platform of a nuclear turbine, which comprises a data processing server, a load database and a material database, wherein the data processing server is connected with the load database and the material database; the load database is used for storing load data and running state data of the nuclear turbine under a plurality of working conditions; the material database is used for storing material performance data of the nuclear turbine; the data processing server is used for acquiring a monitoring instruction, wherein the monitoring instruction is at least one of a service life monitoring instruction, a safety monitoring instruction and a reliability monitoring instruction of the nuclear turbine, and monitoring data corresponding to the monitoring instruction is determined according to the running state data, the load data and the material performance data, and the monitoring data comprises at least one of service life monitoring data, safety monitoring data and reliability monitoring data. The long service life, high safety and high reliability of the nuclear turbine are realized, the monitoring effect of the nuclear turbine is optimized, and the monitoring difficulty is reduced.
Description
Technical Field
The disclosure relates to the technical field of nuclear turbines, in particular to a combined monitoring platform of a nuclear turbine.
Background
The nuclear turbine can bear the action of various damage mechanisms in the operation process, so that the related performance of the nuclear turbine is damaged to a certain extent, and the operation state and other related attribute parameters of the nuclear turbine are affected to a certain extent.
Therefore, how to monitor the relevant state of the nuclear turbine under the action of various damage mechanisms is a problem to be solved at present.
Disclosure of Invention
The present disclosure aims to solve, at least to some extent, one of the technical problems in the related art.
For this reason, this disclosure proposes a combined monitoring platform of nuclear turbine.
The present disclosure provides a joint monitoring platform of a nuclear turbine, comprising: the system comprises a data processing server, a load database and a material database, wherein the data processing server is connected with the load database and the material database; the load database is used for storing load data and running state data of the nuclear turbine under a plurality of working conditions; the material database is used for storing material performance data of the nuclear turbine; the data processing server is configured to obtain a monitoring instruction for the nuclear turbine, where the monitoring instruction is at least one of a lifetime monitoring instruction, a security monitoring instruction, and a reliability monitoring instruction of the nuclear turbine, call the load database and the material database, obtain running state data and load data matched with the monitoring instruction from the load database, and determine monitoring data corresponding to the monitoring instruction according to the matched running state data and load data and the material performance data, where the monitoring data includes at least one of lifetime monitoring data, security monitoring data, and reliability monitoring data.
The combined monitoring platform for the nuclear turbine comprises a data processing server, a load database and a material database, wherein the data server acquires running state data, load data and material performance data corresponding to a monitoring instruction from the load database and the material database which are connected with the data server based on the acquired monitoring instruction, and further acquires monitoring data corresponding to the monitoring instruction. Further, the nuclear turbine is monitored by the combined monitoring platform based on the monitoring data corresponding to the monitoring instruction. According to the combined monitoring platform for the nuclear turbine, effective monitoring coverage of long service life, high safety and high reliability of the nuclear turbine is achieved, the monitoring effect of the nuclear turbine is optimized, and the monitoring difficulty of the nuclear turbine is reduced.
It should be understood that the description herein is not intended to identify key or critical features of the embodiments of the present disclosure, nor is it intended to be used to limit the scope of the present disclosure. Other features of the present disclosure will become apparent from the following specification.
Drawings
The foregoing and/or additional aspects and advantages of the present disclosure will become apparent and readily appreciated from the following description of the embodiments, taken in conjunction with the accompanying drawings, in which:
FIG. 1 is a schematic structural view of a joint monitoring platform of a nuclear turbine according to an embodiment of the present disclosure;
FIG. 2 is a schematic structural view of a joint monitoring platform of a nuclear turbine according to another embodiment of the present disclosure;
FIG. 3 is a schematic structural view of a joint monitoring platform of a nuclear turbine according to another embodiment of the present disclosure;
FIG. 4 is a flow chart of a method for monitoring a combined monitoring platform of a nuclear turbine according to an embodiment of the disclosure;
FIG. 5 is a flow chart of a method of monitoring a combined monitoring platform of a nuclear turbine according to another embodiment of the disclosure;
FIG. 6 is a flow chart of a method for monitoring the life of a nuclear turbine by a combined monitoring platform of the nuclear turbine according to an embodiment of the disclosure;
FIG. 7 is a flow chart of a method for monitoring the life of a nuclear turbine by a combined monitoring platform of the nuclear turbine according to another embodiment of the disclosure;
FIG. 8 is a flow chart of a method for monitoring the life of a nuclear turbine by a combined monitoring platform of the nuclear turbine according to another embodiment of the disclosure;
FIG. 9 is a flow chart of a method of monitoring a combined monitoring platform of a nuclear turbine according to another embodiment of the disclosure;
FIG. 10 is a flow chart of a method for monitoring safety of a nuclear turbine by a combined monitoring platform of the nuclear turbine according to an embodiment of the disclosure;
FIG. 11 is a flow chart of a method for monitoring safety of a nuclear turbine by a combined monitoring platform of the nuclear turbine according to another embodiment of the disclosure;
FIG. 12 is a flow chart of a method for monitoring safety of a nuclear turbine by a combined monitoring platform of the nuclear turbine according to another embodiment of the disclosure;
FIG. 13 is a flow chart of a method of monitoring a combined monitoring platform of a nuclear turbine according to another embodiment of the disclosure;
FIG. 14 is a flow chart of a method for monitoring the reliability of a nuclear turbine by a combined monitoring platform of the nuclear turbine according to an embodiment of the disclosure;
FIG. 15 is a flow chart of a method for monitoring the reliability of a nuclear turbine by a combined monitoring platform of the nuclear turbine according to another embodiment of the disclosure;
FIG. 16 is a flow chart of a method for monitoring the reliability of a nuclear turbine by a combined monitoring platform of the nuclear turbine according to another embodiment of the disclosure.
Detailed Description
Embodiments of the present disclosure are described in detail below, examples of which are illustrated in the accompanying drawings, wherein like or similar reference numerals refer to like or similar elements or elements having like or similar functions throughout. The embodiments described below by referring to the drawings are exemplary and intended for the purpose of explaining the present disclosure and are not to be construed as limiting the present disclosure.
The following describes a joint monitoring platform of a nuclear turbine according to an embodiment of the present disclosure with reference to the accompanying drawings.
Fig. 1 is a schematic structural diagram of a combined monitoring platform of a nuclear turbine according to an embodiment of the disclosure, as shown in fig. 1, a combined monitoring platform 100 of a nuclear turbine includes a data processing server 11, a load database 12, and a material database 13, where the data processing server 11 is connected to the load database 12 and the material database 13.
In the implementation, the nuclear turbine is composed of a plurality of parts, and the operation of the nuclear turbine is realized based on the respective operation and cooperation of each part. In the operation process of the nuclear turbine, the damage mechanism action born by different parts is different, so that the nuclear turbine can bear various damage mechanisms in operation.
For example, the rotor of a nuclear turbine may suffer from low cycle fatigue life damage and high cycle fatigue life damage due to centrifugal force, thermal load, and gravitational load. For another example, the valve casings and cylinders of a nuclear turbine may suffer from low cycle fatigue life damage and creep life damage under pressure and thermal loading. For another example, the rotor, valve housing and cylinder of a nuclear turbine may suffer life damage under rapid start-up thermal stresses.
For example, nuclear turbines may suffer from power degradation and stress corrosion damage due to damage such as scaling, wear, corrosion, and water erosion. For another example, the rotor of a nuclear turbine may have insufficient steady-state and transient strength margins under centrifugal force and thermal load. For another example, under the action of the stress load, the thermal load and the bolt pretightening force load, the cylinder of the nuclear turbine has the possibility of facing the steam leakage risk of the split surface of the cylinder flange. For another example, the valve housing and cylinder of a nuclear turbine may be subject to centrifugal force and thermal loading with insufficient steady-state and transient strength margins.
For example, the rotor blade of a nuclear turbine may be damaged by high-cycle fatigue due to centrifugal force, low-frequency excitation force, and high-frequency excitation force. For another example, when a grid electrical disturbance fault occurs in a multi-rotor system of a nuclear turbine, the possibility of torsional vibration damage exists. For another example, the rotor and bearing system of the nuclear turbine has the possibility of shafting vibration damage under the actions of forced vibration and self-excited vibration.
In the embodiment of the disclosure, the service life, safety and reliability of the nuclear turbine under the action of various damage mechanisms can be monitored through the combined monitoring platform of the nuclear turbine.
As shown in fig. 1, the joint monitoring platform 100 of the nuclear turbine includes a load database 12, where the load database 12 is used to store load data and operation state data of the nuclear turbine under multiple working conditions.
In the embodiment of the disclosure, the nuclear turbine can have a plurality of working conditions, and each working condition has a corresponding working state of the nuclear turbine.
Further, the nuclear turbine is composed of a plurality of components such as a rotor, a valve housing, a cylinder, a rotor blade, a multi-rotor system, a bearing system, and the like. The load and the operation state of each component under different working conditions are different, and further, the load data and the operation state data of each component of the nuclear turbine under each working condition can be stored in the load database 12.
The conditions of the nuclear turbine may include stable conditions, high transients, and the like, among others.
Optionally, data monitoring may be performed on each component of the nuclear turbine, and when the nuclear turbine is in a stable condition, the obtained load data and operation state data of each component of the nuclear turbine under the stable condition may be stored in the load database 12. And, when the nuclear turbine is in a high transient state, the obtained load data and operation state data of each component of the nuclear turbine under the high transient state working condition may be stored in the load database 12.
As shown in fig. 1, the joint monitoring platform 100 of the nuclear turbine further includes a material database 13, wherein the material database 13 is used for storing material performance data of the nuclear turbine.
In the embodiment of the disclosure, the joint monitoring platform 100 of the nuclear turbine is used for monitoring material properties of different components in the nuclear turbine, such as low cycle fatigue life, high cycle fatigue life, steady-state strength, transient strength, low frequency excitation force, high frequency excitation force, and the like of the material.
Therefore, related operations are required to be performed on material performance data of different parts of the nuclear turbine, so as to obtain material performance states under different working conditions. Further, material property data of the components of the nuclear turbine may be stored in the material database 13.
As shown in fig. 1, the joint monitoring platform 100 of the nuclear turbine further includes a data processing server 11, where the data processing server 11 is configured to obtain a monitoring instruction for the nuclear turbine, where the monitoring instruction is at least one of a life monitoring instruction, a safety monitoring instruction, and a reliability monitoring instruction of the nuclear turbine, call a load database and a material database, obtain, from the load database, operation state data and load data that match the monitoring instruction, and determine, according to the matched operation state data and load data, and material performance data, monitoring data corresponding to the monitoring instruction, where the monitoring data includes at least one of life monitoring data, safety monitoring data, and reliability monitoring data.
In the embodiment of the disclosure, the combined monitoring platform 100 of the nuclear turbine can be controlled through the monitoring instruction, so that the combined monitoring platform 100 of the nuclear turbine can monitor the nuclear turbine in different types.
Further, a monitoring instruction for the nuclear turbine may be transmitted to the data processing server 11 of the nuclear turbine. Wherein the monitoring instructions may include at least one of a lifetime monitoring instruction, a security monitoring instruction, and a reliability monitoring instruction.
Optionally, based on the obtained life monitoring instruction for the nuclear turbine, the life of the nuclear turbine can be monitored.
According to the obtained life monitoring instruction, the data processing server 11 may obtain corresponding running state data and load data from the load database 12, and obtain corresponding material performance data from the material database 13, so as to determine life monitoring data corresponding to the life monitoring instruction, and further realize life monitoring of the nuclear turbine.
Optionally, based on the obtained safety monitoring instruction for the nuclear turbine, high safety monitoring of the nuclear turbine can be achieved.
According to the obtained safety monitoring instruction, the data processing server 11 may obtain corresponding running state data and load data from the load database 12, and obtain corresponding material performance data from the material database 13, so as to determine safety monitoring data corresponding to the safety monitoring instruction, thereby implementing high safety monitoring on the nuclear turbine.
Optionally, based on the obtained reliability monitoring instruction for the nuclear turbine, high reliability monitoring of the nuclear turbine can be achieved.
According to the obtained reliability monitoring instruction, the data processing server 11 may obtain corresponding running state data and load data from the load database 12, and obtain corresponding material performance data from the material database 13, so as to determine reliability monitoring data corresponding to the reliability monitoring instruction, thereby implementing high reliability monitoring on the nuclear turbine.
The combined monitoring platform for the nuclear turbine comprises a data processing server, a load database and a material database, wherein the data server acquires running state data, load data and material performance data corresponding to a monitoring instruction from the load database and the material database which are connected with the data server based on the acquired monitoring instruction, and further acquires monitoring data corresponding to the monitoring instruction. Further, the nuclear turbine is monitored by the combined monitoring platform based on the monitoring data corresponding to the monitoring instruction. According to the combined monitoring platform for the nuclear turbine, effective monitoring coverage of long service life, high safety and high reliability of the nuclear turbine is achieved, the monitoring effect of the nuclear turbine is optimized, and the monitoring difficulty of the nuclear turbine is reduced.
In the above embodiment, the combined monitoring platform of the nuclear turbine further includes other modules, and fig. 2 may be combined with fig. 2, where fig. 2 is a schematic structural diagram of the combined monitoring platform of the nuclear turbine according to another embodiment of the disclosure.
As shown in fig. 2, the joint monitoring platform 200 of the nuclear turbine comprises a data processing server 21, a load database 22, a material database 23, a component model database 24, a web page server 25 and a client browser 26, wherein the data processing server 21 is connected with the load database 22 and the material database 23, the component model database 24 is connected with the data processing server 21, the web page server 25 is connected with the data processing server 21, and the client browser 26 is connected with the web page server 25.
In the embodiment of the present disclosure, the load database 22 is used to store load data and operation state data under multiple working conditions of the nuclear turbine, where the load database 22 may store at least one of the following data:
the nuclear turbine is subjected to pressure load, centrifugal force load, thermal load and bolt pretightening force load.
The rigidity coefficient and the damping coefficient of the bearing oil film.
The metal temperature is measured at the depth of 85% -95% of the wall thickness of the inner cylinder.
The metal temperature of the measuring point is 85-95% of the wall thickness of the valve casing and the cylinder, and the metal temperature of the measuring point is 45-50% of the wall thickness of the valve casing and the cylinder.
And the metal temperature outside the flange center plane is under the condition of steam leakage at the weakest part of the flange center plane tightness of the cylinder.
On-line monitoring of peak-to-peak value Dp-pr of relative displacement of shaft vibration of rotor shaft journal of nuclear turbine and on-line monitoring of vibration speed V of bearing seat b 。
Start-stop curve of a nuclear turbine.
A material database 23 for storing material performance data of the nuclear turbine, wherein at least one of the data may be stored in the material database 23: physical properties of materials, mechanical properties of high-temperature long-time and mechanical properties of fatigue fracture of the nuclear turbine.
It will be appreciated that the material database 23 stores performance parameter data of constituent materials of each component constituting the nuclear turbine, wherein the material physical property data, the material mechanical property data, the high-temperature long-time mechanical property data, and the fatigue fracture mechanical property data can be used for generation of monitoring data of the nuclear turbine, such as life monitoring data, safety monitoring data, and reliability monitoring data.
The combined monitoring platform 200 of the nuclear turbine further comprises a component model database 24, wherein the component model database 24 is used for component design parameters and a three-dimensional mechanical model of the nuclear turbine.
The data processing server 21 is further configured to call the component model database 24 after the monitoring instruction is acquired, acquire the component design parameter and the three-dimensional mechanical model from the component model database 24, and determine the monitoring data corresponding to the monitoring instruction based on the component design parameter, the three-dimensional mechanical model, the running state data and the load data matched with the monitoring instruction, and the material performance data.
In implementation, the joint monitoring platform of the nuclear turbine can be controlled by a monitoring instruction, wherein the data processing server 21 can acquire the component design parameters and the three-dimensional mechanical model from the component model database 24 based on the monitoring instruction after acquiring the monitoring instruction.
Optionally, the component design parameters and the three-dimensional mechanical model can be used for long-life and high-reliability monitoring of the nuclear turbine, and the component design parameters, the three-dimensional mechanical parameters, the running state data, the load data and the material performance data matched with the monitoring instruction are combined, so that long-life monitoring data and high-reliability monitoring data corresponding to the long-life monitoring instruction and the high-reliability monitoring instruction are obtained.
In the embodiment of the present disclosure, the data processing server 21 may be further configured to generate an optimization and improvement policy of the nuclear turbine according to the monitoring data, and perform operation optimization control on the nuclear turbine according to the optimization and improvement policy.
In order to realize effective monitoring of the nuclear turbine, after the monitoring data corresponding to the monitoring instruction is obtained, the data processing server 21 can generate an optimization and improvement strategy of the nuclear turbine according to the monitoring data. The optimization improvement strategy can comprise the object to be optimized, parameters to be optimized of the object to be optimized and values of the parameters to be optimized after optimization.
It can be understood that the data processing server 21 can judge the service life, the safety and the reliability of the nuclear turbine according to the monitoring data, and can obtain the optimization and improvement strategy corresponding to the nuclear turbine according to the judging result.
Further, the nuclear turbine is optimized in a related manner according to the optimization and improvement strategy.
Wherein the monitoring data or the optimization improvement strategy information can be fed back to the web server 25 and the client browser 26 for presentation.
In the embodiment of the present disclosure, the joint monitoring platform 200 of the nuclear turbine further includes a web server 25.
The web server 25 is connected to the data processing server 21, where the web server 25 is configured to receive the data sent by the data processing server 21, and render a web page based on the data to generate web page data.
In implementation, there is a visual requirement for related data such as a monitoring condition of the nuclear turbine, so that the related data to be displayed can be sent to the web server 25, and the web server 25 further performs rendering processing according to the acquired related data, so as to generate corresponding web data.
Optionally, the web page server 25 is further configured to receive the monitoring data sent by the data processing server, and render the web page based on the monitoring data to generate the first type of web page data.
The monitoring data of the nuclear turbine has a visual requirement, so the web server 25 can further process the monitoring data transmitted by the data processing server 21, further generate web data corresponding to the monitoring data, and determine the web data as the first type of web data.
Optionally, the web page server 25 is further configured to receive the optimization improvement policy sent by the data processing server, and render the web page based on the optimization improvement policy to generate the second type of web page data.
The optimization and improvement strategy of the nuclear turbine has a visual requirement, so the web server 25 can further process the optimization and improvement strategy transmitted by the data processing server 21, further generate web data corresponding to the optimization and improvement strategy, and determine the web data as the second type of web data.
Further, the webpage data can be visually displayed through a client browser.
In the embodiment of the disclosure, the joint monitoring platform 200 of the nuclear turbine further includes a client browser 26.
The client browser 26 is connected to the web server 25, where the client browser 26 is configured to respond to a browsing instruction input by a user, send the browsing instruction to the web server 25, and receive web page data sent by the web server 25 for display.
In an implementation, the user may input a browsing instruction through the client browser 26, where the browsing instruction may include related attribute information of data that the user needs to browse. After the client browser 26 sends the browsing instruction to the web server 25, the web server 25 may retrieve, according to the attribute information carried in the browsing instruction, the web data corresponding to the data that the user needs to browse, and transmit the web data to the client browser 26.
Further, based on the display interface of the client browser 26, the webpage data corresponding to the browsing instruction is displayed.
The combined monitoring platform of the nuclear turbine comprises a data processing server, a load database, a material database, a component model database, a web server and a client browser, wherein the data processing server is connected with the load database, the material database, the component model database and the web server, and the client browser is connected with the web server. Through the connection relation among different functional modules, data interaction among different functional modules is realized, and further effective monitoring coverage of long service life, high safety and high reliability of the nuclear turbine is realized, the monitoring effect of the nuclear turbine is optimized, and the monitoring difficulty of the nuclear turbine is reduced.
In order to realize effective monitoring of the long service life, high safety and high reliability of the nuclear turbine, the combined monitoring platform of the nuclear turbine provided by the disclosure is of a distributed network structure, and can be combined with fig. 3, and fig. 3 is a schematic structural diagram of the combined monitoring platform of the nuclear turbine according to another embodiment of the disclosure.
As shown in fig. 3, the joint monitoring platform of the nuclear turbine includes a scheduling server, a plurality of data processing servers and a plurality of web servers.
The scheduling server is used for receiving the monitoring instruction, scheduling the monitoring instruction, determining a target data processing server and a target webpage server corresponding to the monitoring instruction, and sending identification information of the monitoring instruction and the target webpage server to the target data processing server.
In the embodiment of the disclosure, the combined monitoring platform of the nuclear turbine can be of a distributed network structure so as to realize effective monitoring of the nuclear turbine in the same time period.
Further, multi-dimensional monitoring of the nuclear turbine can be achieved through the scheduling server.
In the implementation, the distributed network structure of the combined monitoring platform of the nuclear turbine can be composed of different local networks, wherein the different local networks can monitor different dimensionalities of the nuclear turbine.
Alternatively, the scheduling server may configure the relevant information of the target data processing server and the target web server for the monitoring instruction according to the availability status of each data processing server and the web server.
Wherein the availability status of the data processing server may be determined as a first load status and the availability status of the web server may be determined as a second load status.
Further, a first load state of each data processing server and a second load state of each web server are obtained. And scheduling the monitoring instruction according to the first load state and the second load state, and determining the target data processing server and the target web server.
Optionally, the occupied space and the unoccupied space of the data processing server may be determined according to the first load state, and further, whether the data processing server may implement execution of the monitoring instruction is determined according to the unoccupied space in the data processing server, so as to determine a target data processing server corresponding to the monitoring instruction.
Accordingly, the occupied space and the unoccupied space of the web server can be determined according to the second load state, and further, whether the web server can process and generate the monitoring data corresponding to the monitoring instruction and the optimizing and improving strategy according to the unoccupied space in the web server is judged, so that the target web server corresponding to the monitoring instruction is determined.
In order to realize accurate data interaction between the target data processing server and the target web server, the scheduling server may transmit the identification information of the target web server and the monitoring instruction to the target data processing server.
Further, the target data processing server is configured to receive the monitoring instruction, process the monitoring instruction, generate corresponding data, and send the corresponding data corresponding to the monitoring instruction to the target web server based on the identification information.
It will be appreciated that the target data processing server may transmit the generated monitoring data and the corresponding optimization improvement policy to the corresponding target web server based on the identification information of the target web server.
The combined monitoring platform of the nuclear turbine can realize a distributed network structure through the scheduling server, wherein the combined monitoring platform of the nuclear turbine comprises a plurality of data processing servers and a plurality of web servers. Further, the scheduling server can determine available target data processing servers and target webpage servers for the monitoring instructions according to the first load state of the data processing servers and the second load state of the webpage servers, so that the combined monitoring platform of the nuclear turbine can execute a plurality of monitoring instructions simultaneously. In the method, the monitoring coverage of the combined monitoring platform of the nuclear turbine on the nuclear turbine is optimized, the monitoring efficiency of the combined monitoring platform of the nuclear turbine is improved, and the monitoring effect of the combined monitoring platform of the nuclear turbine is optimized.
In the above embodiment, regarding the determination of the target monitoring object and the target monitoring dimension of the nuclear turbine by the data processing server, it may be further understood with reference to fig. 4, and fig. 4 is a schematic flow chart of a monitoring method of the joint monitoring platform of the nuclear turbine according to an embodiment of the disclosure, as shown in fig. 4, where the method includes:
s401, determining a target monitoring object and a target monitoring dimension of the nuclear turbine based on the monitoring instruction.
In the embodiment of the disclosure, the joint monitoring platform of the nuclear turbine can monitor any object with a monitoring requirement in the nuclear turbine and determine the object as a target monitoring object of the nuclear turbine, wherein the target monitoring object can comprise the service life, the operation safety, the operation reliability and the like of the nuclear turbine.
Further, different monitoring requirements exist for different target monitoring objects, and the combined monitoring platform of the nuclear turbine can provide monitoring of multiple dimensions for the target monitoring objects. Therefore, after the target monitoring object is determined, the corresponding target monitoring dimension can be determined according to the monitoring requirement of the target monitoring object, wherein different target monitoring dimensions corresponding to the target monitoring object can be determined according to different component parts of the nuclear turbine.
For example, a target monitoring object is set as a lifetime for a rotor of a nuclear turbine. When the rotor is subjected to centrifugal force, thermal load and gravitational load, the low cycle fatigue life and the high cycle fatigue life thereof may be damaged, and therefore, the low cycle fatigue life and the high cycle fatigue life can be taken as target monitoring dimensions when the rotor is monitored for life based on a target monitoring object.
For another example, the target object to be monitored is set to be safe for the valve housing and the cylinder of the nuclear turbine. When the valve housing and the cylinder bear pressure and thermal load, the steady-state strength and the transient strength of the valve housing and the cylinder are possibly changed, so that the steady-state strength and the transient strength can be used as target monitoring dimensions when the valve housing and the cylinder are monitored safely based on target monitoring objects.
For another example, the target monitoring object is set to be reliable for the rotor blade of the nuclear turbine. When the moving blade is subjected to centrifugal force, low-frequency exciting force and high-frequency exciting force, the moving strength and vibration safety of the moving blade are possibly changed, so that the moving strength and vibration safety can be used as target monitoring dimensions when the moving blade is reliably monitored based on a target monitoring object.
S402, according to the target monitoring object and the target monitoring dimension, acquiring running state data matched with the target monitoring object and the target monitoring dimension from a load database.
In the embodiment of the disclosure, the load database stores the operation state data and the load data of the nuclear turbine, and the data processing server can acquire the operation state data of the target monitoring object and the matching of the target monitoring dimension from the load database.
For example, the target monitoring object is set as the safety of the nuclear turbine, and the target monitoring dimension is tightness of the flange center plane acted by the bearing load, the heat load and the bolt pretightening load of the cylinder, so that the running state data of the flange center plane of the cylinder in the tightness dimension can be obtained from a load database, the tightness data of the flange center plane of the cylinder when the corresponding force load is born, the tightness data of the flange center plane of the cylinder when the corresponding heat load is born can be included, and the tightness data of the flange center plane of the cylinder when the corresponding bolt pretightening load is born can be included.
For another example, the target monitoring object is set as the service life of the nuclear turbine, and the target monitoring dimension is the service life of the rotor, the valve housing and the cylinder under the action of the rapid start thermal stress, so that the service life data of the rotor, the valve housing and the cylinder under the action of the rapid start thermal stress can be obtained from the load database.
For another example, the target monitoring object is set as the reliability of the nuclear turbine, and the target monitoring dimension is that the rotor and the bearing system bear shafting vibration safe operation under the action of forced vibration and self-excitation vibration, so that shafting vibration monitoring data of the rotor and the bearing system when bearing the action of forced vibration and self-excitation vibration can be obtained from the load database.
S403, determining monitoring data corresponding to the monitoring instruction according to the matched running state data, material performance data, component design parameters and the three-dimensional mechanical model.
In the embodiment of the disclosure, the monitoring data of the target monitoring object in the target monitoring dimension can be obtained according to the running state data, the material performance data, the component design parameters and the three-dimensional mechanical model.
The data processing server can acquire running state data, material performance data, component design parameters and a three-dimensional mechanical model according to the received monitoring instruction. Based on the execution of the monitoring instruction, the data processing server can acquire running state data corresponding to the target monitoring object in the target monitoring dimension from the load database, acquire material performance data corresponding to the target monitoring object in the target monitoring dimension from the material database, and acquire component design parameters corresponding to the target monitoring object in the target monitoring dimension and a corresponding three-dimensional mechanical model from the component model database.
Further, based on the related data matched from different databases, the monitoring data corresponding to the monitoring instruction is obtained.
According to the combined monitoring platform of the nuclear turbine, the data processing server determines a target monitoring object and a target monitoring dimension according to the monitoring instruction, so that matched running state data, material performance data, component design parameters and a three-dimensional mechanical model of the target monitoring object and the target monitoring dimension are obtained, and monitoring data corresponding to the monitoring instruction are obtained. In the method, based on integration of related data in different databases, the monitoring data corresponding to the monitoring instruction is obtained, accuracy of the monitoring data is guaranteed, and further optimization of the monitoring effect of the nuclear turbine is achieved.
The combined monitoring platform for the nuclear turbine provided by the disclosure can realize service life monitoring of the nuclear turbine, and can be further understood with reference to fig. 5, and fig. 5 is a schematic flow chart of a monitoring method for the combined monitoring platform for the nuclear turbine according to another embodiment of the disclosure, as shown in fig. 5, the method includes:
s501, when the monitoring instruction is a life monitoring instruction, acquiring running state data and load data matched with the life monitoring instruction and material performance data.
In the embodiment of the disclosure, the combined monitoring platform of the nuclear turbine can receive the monitoring instruction, wherein the monitoring instruction can be a service life monitoring instruction for the nuclear turbine, and the combined monitoring platform of the nuclear turbine can monitor the service life of the nuclear turbine according to the received service life monitoring instruction.
Further, a service life monitoring instruction can be received through a data processing server in a combined monitoring platform of the nuclear turbine, and matched service life monitoring data can be obtained according to the service life monitoring instruction.
In the implementation, the service life of the nuclear turbine is greatly related to the running state, the bearing load and the material performance of the nuclear turbine, so that the service life monitoring data matched with the service life monitoring instruction can be determined by acquiring corresponding running state data, load data and material performance data.
The data processing server can acquire the operation state data and the load data matched with the service life monitoring instruction and the material performance data from a database connected with the data processing server.
S502, based on the running state data and the load data matched with the service life monitoring instruction and the material performance data, acquiring at least one of the following data:
Acquiring first life monitoring data of low cycle fatigue and high cycle fatigue of a rotor of a nuclear turbine under a plurality of working conditions under the actions of centrifugal force, thermal load and gravity load;
acquiring second life monitoring data of low cycle fatigue and creep under the pressure and thermal load bearing actions of a valve housing and a cylinder of a nuclear turbine under multiple working conditions;
acquiring third service life monitoring data of a rotor, a valve housing and a cylinder of the nuclear turbine under the multi-working condition of bearing the rapid starting thermal stress;
and determining the first life monitoring data, the second life monitoring data and the third life monitoring data as life monitoring data of the nuclear turbine.
In the operation process of the nuclear turbine, the service life of part of components in the nuclear turbine is possibly damaged. For example, in the rotor of a nuclear turbine, the low cycle fatigue life and the high cycle fatigue life of the rotor may be damaged during the operation of the nuclear turbine. For example, in the valve casing of a nuclear turbine, the creep life and the low cycle fatigue life of the valve casing may be damaged during the operation of the nuclear turbine.
Further, the data processing server may acquire at least one of the operation state data, the load data, and the material property data, which are matched with the lifetime monitoring instruction, as the corresponding lifetime monitoring data based on the lifetime monitoring instruction.
Optionally, the data processing server may obtain first life monitoring data of low cycle fatigue and high cycle fatigue of the rotor of the nuclear turbine subjected to centrifugal force, thermal load and gravitational load under a plurality of working conditions.
In the embodiment of the disclosure, during the operation process of the nuclear turbine, the rotor of the nuclear turbine can bear the effects of centrifugal force, thermal load and gravity load, so that the damage possibility of the low cycle fatigue life and the high cycle fatigue life of the rotor is caused.
The rotor is subjected to different centrifugal forces, thermal loads and gravitational loads under different working conditions, so that the low cycle fatigue life and the high cycle fatigue life of the rotor under different working conditions may be different.
Further, in order to realize life monitoring of the rotor, the data processing server may acquire low cycle fatigue life data and high cycle fatigue life data of the rotor of the nuclear turbine subjected to centrifugal force, thermal load and gravitational load under a plurality of working conditions as corresponding life monitoring data, and determine the corresponding life monitoring data as first life monitoring data.
For example, the low cycle fatigue life data and the high cycle fatigue life data of the rotor subjected to the centrifugal force, the thermal load and the gravity load under the stable working condition can be used as the first life monitoring data, and the low cycle fatigue life data and the high cycle fatigue life data of the rotor subjected to the centrifugal force, the thermal load and the gravity load under the high transient working condition can be used as the first life monitoring data.
Optionally, second life monitoring data of low cycle fatigue and creep under pressure and thermal load of the valve housing and the cylinder of the nuclear turbine is obtained.
In the embodiment of the disclosure, the valve housing and the cylinder of the nuclear turbine can bear the effects of pressure and thermal load in the operation process of the nuclear turbine, so that the valve housing and the cylinder of the nuclear turbine have the possibility of damage to the low cycle fatigue life and the creep life.
The valve housing and the cylinder of the nuclear turbine are different in the effects of pressure and thermal load under different working conditions, so that the low cycle fatigue life and creep life of the valve housing and the cylinder under different working conditions can be different.
Further, in order to realize life monitoring of the valve casing and the cylinder of the nuclear turbine, the data processing server may acquire low cycle fatigue life data and creep life data of the valve casing and the cylinder of the nuclear turbine under the action of pressure and thermal load under a plurality of working conditions as corresponding life monitoring data, and determine the corresponding life monitoring data as second life monitoring data.
For example, the low cycle fatigue life data and creep life data of the valve housing and the cylinder subjected to the pressure and the thermal load under the stable working condition can be used as the second life monitoring data, and the low cycle fatigue life data and creep life data of the valve housing and the cylinder subjected to the pressure and the thermal load under the high transient working condition can be used as the second life monitoring data.
Optionally, third life monitoring data of the rotor, the valve housing and the cylinder of the nuclear turbine, which bear the effect of rapid start thermal stress under the multiple working conditions, are obtained.
In practice, there is a need for a fast start-up of a nuclear turbine. When the nuclear turbine needs to be started quickly, part of components such as a rotor, a valve housing and a cylinder can bear the action of thermal stress caused by the quick start, and the service life of the part of components such as the rotor, the valve housing and the cylinder of the nuclear turbine can be damaged.
The data processing server can acquire service life data of the rotor, the valve casing and the cylinder when the rotor, the valve casing and the cylinder bear the rapid start thermal stress and take the service life data as third service life monitoring data.
For example, life data of the rotor, the valve housing and the cylinder subjected to the rapid start thermal stress under the stable working condition can be used as third life monitoring data, and life data of the valve housing and the cylinder subjected to the rapid start thermal stress under the high transient working condition can be used as third life monitoring data.
Further, the first life monitoring data, the second life monitoring data and the third life monitoring data are determined to be life monitoring data of the nuclear turbine.
In the embodiment of the disclosure, the first life monitoring data includes low cycle fatigue and high cycle fatigue life monitoring data of a rotor of the nuclear turbine when subjected to centrifugal force, thermal load and gravitational load, the second life monitoring data includes low cycle fatigue and creep life monitoring data of a valve casing and a cylinder of the nuclear turbine when subjected to pressure and thermal load, and the third life monitoring data includes life monitoring data of the rotor, the valve casing and the cylinder of the nuclear turbine when subjected to rapid start thermal stress.
Based on the first life monitoring data, the second life monitoring data and the third life monitoring data, effective monitoring coverage can be realized for components needing to be subjected to life monitoring in the nuclear turbine.
Further, the data processing server can acquire at least one of the first life monitoring data, the second life monitoring data and the third life monitoring data from a corresponding database in the combined monitoring platform of the nuclear turbine, so as to further determine the life monitoring data matched with the life monitoring instruction.
According to the combined monitoring platform of the nuclear turbine, the service life of the nuclear turbine is monitored according to the acquired service life monitoring instruction, at least one of first service life monitoring data, second service life monitoring data and third service life monitoring data corresponding to the nuclear turbine is acquired from the corresponding database, and further service life monitoring data of the nuclear turbine matched with the service life monitoring instruction is determined. In the method, the service life of the nuclear turbine is monitored through the service life monitoring data, the service life monitoring effect of the nuclear turbine is optimized, and the service life of the nuclear turbine is monitored.
In order to better understand the implementation of the optimization and improvement strategy of the nuclear turbine, which is performed by the combined monitoring platform of the nuclear turbine on the service life of the nuclear turbine and is determined based on the service life monitoring result, the following embodiments may be further combined.
In the practical application scene, when the rotor of the nuclear turbine bears centrifugal force, thermal load and gravity load, the low cycle fatigue life and the high cycle fatigue life of the rotor are possibly damaged. Further, long-life design monitoring can be performed on the rotor of the nuclear turbine bearing centrifugal force, thermal load and gravity load, wherein the low-cycle fatigue life and the high-cycle fatigue life reach 60 years, and as can be understood with reference to fig. 6, fig. 6 is a schematic flow chart of a method for monitoring the life of the nuclear turbine by the combined monitoring platform of the nuclear turbine according to an embodiment of the disclosure, as shown in fig. 6, the method includes:
s601, determining the start-stop times of the nuclear turbine.
Method and subroutine for monitoring low cycle fatigue and high cycle fatigue life design, based on load database, inputting annual average cold start times y of nuclear turbine c Number of times y of annual average temperature state start w Number of times y of annual average hot start h Number y of normal stop times per year n Number y of overspeed tests of 110% in annual average 110 Number of operating hours per year t y Operating speed n 0 。
For example, for a 1200MW nuclear turbine of a certain model, based on a load database, the annual average cold state starting times y of the 1200MW nuclear turbine of the model is input c Number of times y of annual average temperature state start w Number of times y of annual average hot start h Number y of normal stop times per year n Number y of overspeed tests of 110% in annual average 110 Number of operating hours per year t y Operating speed n 0 The specific results are shown in Table 1.
Table 1 number of start-up and shut-down times for steam turbines
| Sequence number | | Index value | |
| 1 | Number of times y of annual cold state start c /times | 4 | |
| 2 | Number of times y of annual average temperature state start w /times | 20 | |
| 3 | Number of times y of annual average hot state start h /times | 75 | |
| 4 | Number y of annual average normal shutdown times n /times | 99 | |
| 5 | Number y of annual average 110% overspeed tests 110 / |
1 | |
| 6 | Number of operating hours per year t y /h | 7000 | |
| 7 | Operating rotational speed n 0 /r/min | 1500 |
S602, calculating first crack initiation life parameters of low cycle fatigue and high cycle fatigue of a rotor of the nuclear turbine.
Based on a component model database, a load database and a material database, inputting design parameters and a three-dimensional mechanical model of a nuclear turbine rotor, centrifugal force, thermal load and gravity load of the nuclear turbine rotor and blades and material performance data, determining a part with the largest high cycle fatigue stress amplitude under steady-state rated working conditions as a life weak part of the nuclear turbine rotor by using a method and a subprogram for designing and monitoring low cycle fatigue and high cycle fatigue life, and calculating to obtain the cold start-stop low cycle fatigue crack initiation life N of the life weak part of the nuclear turbine rotor ic Low cycle fatigue crack initiation life N at start and stop at temperature iw Low cycle fatigue crack initiation life N for thermal start-stop ih Low cycle fatigue crack initiation life N during 110% overspeed test i110 Rotor high cycle fatigue crack initiation life N iH 。
For example, a part with the largest high cycle fatigue stress amplitude under the steady-state rated working condition is determined as a weak service life part of the rotor of the 1200MW nuclear turbine, wherein the weak service life part is a root fillet part of a turbine blade on the steam exhaust side, and the weak service life part has a cold start-stop low cycle fatigue crack initiation life N ic Low cycle fatigue crack initiation life N at start and stop at temperature iw Low cycle fatigue crack initiation life N for thermal start-stop ih Low cycle fatigue crack initiation life N during 110% overspeed test i110 Rotor high cycle fatigue crack initiation life N iH The specific results are shown in Table 2.
Table 2 low cycle fatigue and high cycle fatigue crack for steam turbine rotor under the i-th operating conditionGrain sprouting life N i
| Sequence number | Working conditions of | Crack initiation life N i / |
| 1 | Low cycle fatigue during cold start-stop | N ic ＝18900 |
| 2 | Low cycle fatigue with warm start-stop and start-stop | N iw ＝20500 |
| 3 | Thermal state start-stop low cycle fatigue | N ih ＝19900 |
| 4 | 110% overspeed test low cycle fatigue | N i110 ＝6900 |
| 5 | High cycle fatigue in loaded operation | N iH ＝9.5×10 9 |
S603, calculating first crack expansion life parameters of low cycle fatigue and high cycle fatigue of the nuclear turbine rotor.
Based on the component model database, the load database and the material database, the design parameters and the three-dimensional mechanical model of the nuclear turbine rotor, the centrifugal force, the thermal load and the gravity load of the rotor and the blades of the nuclear turbine and the material performance data are input, and the low cycle fatigue and high cycle fatigue life design monitoring method and the subprogram are used for calculating the first-stage cold start low cycle fatigue crack expansion life N of the weak part of the life of the nuclear turbine rotor pc,1 Low cycle fatigue crack growth life N in first stage warm start pw,1 First stage hot start low cycle fatigue crack growth life N ph,1 Low cycle fatigue crack growth life N during first stage normal shut down pn,1 First stage 110% overspeed test low cycle fatigue crack growth life N p110,1 Second stage cold start low cycle fatigue crack growth life N pc 2, second stage temperature start low cycle fatigue crack growth life N pw,2 Second stage hot start low cycle fatigue crack growth life N ph,2 Second stage normal stop low cycle fatigue crack growth life N pn,2 Second stage 110% overspeed test low cycle fatigue crack growth life N p110,2 Rotor high cycle fatigue crack growth life N pH 。
For example, design parameters and a three-dimensional mechanical model of the 1200MW nuclear turbine rotor, centrifugal force, thermal load and gravity load of the nuclear turbine rotor and blades, and material performance data are input, and a low cycle fatigue and high cycle fatigue life design monitoring method is used to calculate a first stage cold start low cycle fatigue crack growth life N of a weak part of the 1200MW nuclear turbine rotor life pc,1 Low cycle fatigue crack growth life N in first stage warm start pw,1 First stage hot start low cycle fatigue crack growth life N ph,1 Low cycle fatigue crack growth life N during first stage normal shut down pn,1 First stage 110% overspeed test low cycle fatigue crack growth life N p110,1 Second stage cold start low cycle fatigue crack growth life N pc,2 Low cycle of second stage warm startFatigue crack growth life N pw,2 Second stage hot start low cycle fatigue crack growth life N ph,1 Second stage normal stop low cycle fatigue crack growth life N pn,2 Second stage 110% overspeed test low cycle fatigue crack growth life N p110,2 Rotor high cycle fatigue crack growth life N pH The specific results are shown in Table 3.
TABLE 3 Low cycle fatigue and high cycle fatigue crack growth Life N for rotors pi
S604, calculating the annual average high cycle fatigue times of the rotor of the nuclear turbine.
Annual average high cycle fatigue frequency y of nuclear turbine rotor H The calculation is carried out according to the following formula:
wherein t is y For the annual operating hours of the nuclear turbine, n 0 Is the working rotation speed.
For example, the model 1200MW nuclear turbine rotor has a number y of annual average high cycle fatigue H The calculation is carried out according to the following formula:
in the above formula, t y The annual average operation hours of the nuclear turbine are 70000 hours, n 0 The working rotation speed is 1500r/min.
S605, calculating the total service life of the outer surface of the rotor of the nuclear turbine.
Total life tau of outer surface of rotor of nuclear turbine CLto The calculation is carried out according to the following formula:
for example, the weak part of the life of the 1200MW nuclear turbine rotor is the root fillet part of the exhaust side impeller, and the weak part of the life is positioned on the outer surface of the rotor, and the total life tau of the weak part of the life is CLts The calculation is carried out according to the following formula:
s606, calculating the total service life of the inner surface of the rotor of the nuclear turbine.
Total life τ of inner part of rotor of nuclear turbine CLti The calculation is carried out according to the following formula:
for example, since the weak part of the life of the 1200MW nuclear turbine rotor is the rounded part of the root of the turbine blade on the exhaust side, the weak part of the life is positioned on the outer surface of the rotor, and tau CLti ＞τ CLts 。
S607, determining the total service life of the rotor of the nuclear turbine.
Total life τ of rotor of nuclear turbine CLt The calculation is carried out according to the following formula:
τ CLt ＝min{τ CLto ,τ CLti }
for example, the total life τ of the 1200MW nuclear turbine rotor CLt The calculation is carried out according to the following formula:
τ CLt ＝min{τ CLts ,τ CLti }＝min{τ CLts ,τ CLti ＞τ CLts }＝τ CLts = 66.74 years
S608, performing operation optimization control on low cycle fatigue and high cycle fatigue life of the nuclear turbine rotor.
The low cycle fatigue and the high cycle fatigue life of the nuclear turbine rotor are optimally controlled by a design monitoring method for the low cycle fatigue and the high cycle fatigue life of the nuclear turbine rotor bearing centrifugal force, thermal load and gravitational load:
(1) If τ CLt And the design monitoring of the low cycle fatigue and the high cycle fatigue life of the nuclear turbine rotor bearing centrifugal force, thermal load and gravitational load is qualified more than or equal to 60 years, and the design monitoring of the low cycle fatigue and the high cycle fatigue life of the nuclear turbine rotor is finished.
(2) If τ CLt The design and monitoring of low cycle fatigue and high cycle fatigue life of the nuclear turbine rotor bearing centrifugal force, thermal load and gravity load are disqualified in less than 60 years, which shows that materials with better mechanical performance need to be changed in the design stage, the material design, the structural size, the structural fillets and the like are subjected to operation optimization control improvement, and S601 to S608 are re-executed until tau is reached CLt Not less than 60 years; for example, the low cycle fatigue and high cycle fatigue life of the 1200MW nuclear turbine rotor are optimally controlled.
For example, due to τ CLt The design monitoring of the low cycle fatigue and the high cycle fatigue life of the model 1200MW nuclear turbine rotor bearing centrifugal force, thermal load and gravity load is qualified, and the design monitoring of the low cycle fatigue and the high cycle fatigue life of the model 1200MW nuclear turbine rotor is controlled, and the design monitoring of the low cycle fatigue and the high cycle fatigue life of the model 1200MW nuclear turbine rotor is finished and enters the process of the design monitoring of the valve housing and the cylinder life.
According to the embodiment of the disclosure, the total service life of the rotor is obtained, and when the total service life of the rotor is less than the monitoring qualification condition, the rotor is optimally controlled to operate, so that the service life of the rotor of the nuclear turbine can reach the qualification condition.
In the practical application scene, when the valve shell and the cylinder of the nuclear turbine bear the action of pressure and thermal load, the low cycle fatigue life and the creep life of the nuclear turbine are possibly damaged. Further, the long-life design monitoring can be performed on the low cycle fatigue and creep life of the valve casing and the cylinder of the nuclear turbine bearing the pressure and the thermal load effect for 60 years, and as can be understood with reference to fig. 7, fig. 7 is a schematic flow chart of a method for monitoring the life of the nuclear turbine by the combined monitoring platform of the nuclear turbine according to another embodiment of the disclosure, as shown in fig. 7, the method includes:
s701, determining the start-stop times of the nuclear turbine.
Method and subroutine for low cycle fatigue and creep life design monitoring of valve housing and cylinder of nuclear turbine based on load database, and input annual average cold start times y of nuclear turbine c Number of times y of annual average temperature state start w Number of times y of annual average hot start h Number y of normal stop times per year n Number of operating hours per year t y 。
For example, for a 1200MW nuclear turbine of a certain model, based on a load database, the annual average cold state starting times y of the 1200MW nuclear turbine of the model is input c Number of times y of annual average temperature state start w Number of times y of annual average hot start h Number y of normal stop times per year n Number of operating hours per year t y The specific results are shown in Table 4.
Table 4 number of start-up and shut-down times for steam turbines
| Sequence number | | Index value | |
| 1 | Number of times y of annual cold state start c /times | 4 | |
| 2 | Number of times y of annual average temperature state start w /times | 20 | |
| 3 | Number of times y of annual average hot state start h /times | 75 | |
| 4 | Number y of annual average normal shutdown times n /times | 99 | |
| 5 | Number of operating hours per year t y /h | 7000 |
S702, calculating second crack initiation life parameters of low cycle fatigue and creep of a valve casing and a cylinder of the nuclear turbine.
Based on a component model database, a load database and a material database of the nuclear turbine, inputting design parameters and a three-dimensional mechanical model of the nuclear turbine, pressure and thermal load of a valve casing and a cylinder of the nuclear turbine and material performance data, determining weak service life parts of the valve casing and the cylinder of the nuclear turbine by using a method and a subprogram for low cycle fatigue and creep life design monitoring, and calculating to obtain the cold start-stop low cycle fatigue crack initiation life N of the weak service life parts of the valve casing and the cylinder of the nuclear turbine c Low cycle fatigue crack initiation life N at start and stop at temperature w Low cycle fatigue crack initiation life N for thermal start-stop h Creep crack initiation life τ for valve casings and cylinders c The method comprises the steps of carrying out a first treatment on the surface of the Steam inlet temperature for pressurized water reactor nuclear turbine<The valve shell and the cylinder can not creep at 300 ℃ and the creep crack initiation life tau is treated c Is infinity ≡h, but for the steam inlet temperature of a four-generation nuclear turbine such as a high-temperature gas cooled reactor and the like, the creep crack initiation life tau of a valve shell and a cylinder needs to be calculated c 。
For example, based on a nuclear turbineThe method comprises the steps of inputting design parameters and a three-dimensional mechanical model of a model 1200MW nuclear turbine, pressure and thermal load of a model 1200MW nuclear turbine valve housing and a cylinder and material performance data, determining that the weak service life part of the model 1200MW nuclear turbine valve housing and the cylinder is the maximum transient stress inner cylinder outer surface steam inlet side steam inlet pipe and inner cylinder transition fillet by using a low cycle fatigue and creep service life design monitoring method, calculating to obtain the cold start-stop low cycle fatigue crack initiation service life N of the weak service life part of the model 1200MW nuclear turbine valve housing and the cylinder c Low cycle fatigue crack initiation life N at start and stop at temperature w Low cycle fatigue crack initiation life N for thermal start-stop h The results are shown in Table 5, and since the 1200MW nuclear turbine is a pressurized water reactor nuclear turbine, the inlet steam temperature t 01 No creep deformation of valve housing and cylinder at 280.3 deg.c (but for four-generation nuclear turbine such as high temperature gas cooled reactor, creep life damage must be considered due to its steam inlet temperature being higher than 500 deg.c), creep crack initiation life τ of the weak life part is treated c Infinity ≡h; that is, creep life accumulated loss at the weak life part of the valve casing and the cylinder is 60X 7000/tau c ＝0。
TABLE 5 Low cycle fatigue and creep crack initiation life N for valve casings and cylinders of steam turbines i
S703, calculating second crack extension life parameters of low cycle fatigue and creep of the valve housing and the cylinder of the nuclear turbine.
Based on a component model database, a load database and a material database of the nuclear turbine, the design parameters and the three-dimensional mechanical model of the nuclear turbine, and the pressure and the heat load of a valve casing and a cylinder of the nuclear turbine are inputLoad and material performance data, and using a method and a subroutine for low cycle fatigue and creep life design monitoring to calculate the cold start low cycle fatigue crack growth life N of the valve housing and the life weak part of the cylinder of the nuclear turbine fc Low cycle fatigue crack growth life N for warm start fw Thermal start low cycle fatigue crack growth life N fh Normal stop low cycle fatigue crack growth life N fn Creep crack growth life τ of valve housing and cylinder fc The method comprises the steps of carrying out a first treatment on the surface of the Steam inlet temperature for pressurized water reactor nuclear turbine<The valve shell and the cylinder can not creep at 300 ℃ and the creep crack is treated to expand the service life tau fc Is infinity ≡h, but for the steam inlet temperature of a four-generation nuclear turbine such as a high-temperature gas cooled reactor and the like, the creep rupture extension life tau of a valve shell and a cylinder needs to be calculated fc 。
For example, based on a component model database, a load database and a material database of a nuclear turbine, design parameters and a three-dimensional mechanical model of the 1200MW nuclear turbine, pressure and thermal load of valve casings and cylinders of the 1200MW nuclear turbine and material performance data are input, and a cold start low cycle fatigue crack extension life N of life weak parts of the valve casings and cylinders of the 1200MW nuclear turbine is calculated by using a low cycle fatigue and creep life design monitoring method fc Low cycle fatigue crack growth life N for warm start fw Thermal start low cycle fatigue crack growth life N fh Normal stop low cycle fatigue crack growth life N fn The results are shown in Table 6, for the inlet steam temperature of the pressurized water reactor nuclear turbine<The valve casing and the cylinder can not creep at 300 ℃, and the creep crack of the weak life part is treated to expand the life tau fc Is infinity ≡h (but for the steam inlet temperature of a four-generation nuclear turbine such as a high-temperature gas cooled reactor and the like, the creep rupture extension life tau of a valve shell and a cylinder needs to be calculated fc )。
TABLE 6 Low cycle fatigue and creep crack growth life N for valve casings and cylinders of steam turbines fi
| Sequence number | Working conditions of | Crack |
| 1 | Low cycle fatigue during cold start-stop | N fc =1890 times |
| 2 | Low cycle fatigue with warm start-stop and start-stop | N fh =2310 times |
| 3 | Thermal state start-stop low cycle fatigue | N fh =3620 times |
| 4 | Creep under load operation | τ fc ＝∞h |
S704, calculating the total service life of the outer surfaces of the valve housing and the cylinder of the nuclear turbine.
Total life tau of outer surface of valve casing and cylinder of nuclear turbine CLtoc The calculation is carried out according to the following formula:
for example, the valve casing and the valve casing of the 1200MW nuclear turbineTotal life τ of outer surface of cylinder life weak part CLtoc The calculation is carried out according to the following formula:
s705, calculating the total service life of the valve housing of the nuclear turbine and the inner surface of the cylinder.
Total internal life τ of valve casing and cylinder of nuclear turbine CLtic The calculation is carried out according to the following formula:
for example, the model 1200MW nuclear power internal total lifetime τ CLtic The calculation is carried out according to the following formula: because the weak life part of the valve casing and the cylinder of the 1200MW nuclear turbine is the transition fillet of the steam inlet pipe on the steam inlet side of the outer surface of the inner cylinder with the largest transient stress, the weak life part is positioned on the outer surface of the inner cylinder, tau CLtic ＞τ Cltoc 。
S706, determining the total service life of the valve housing and the cylinder of the nuclear turbine.
Total life tau of weak life part of valve casing and cylinder of nuclear turbine CLt The calculation is carried out according to the following formula:
τ CLtc ＝min{τ CLtoc ,τ CLtic }
for example, the total service life tau of the valve housing and the weak service life part of the cylinder of the 1200MW nuclear turbine CLtc The calculation is carried out according to the following formula:
τ CLtc ＝min{τ CLtoc ,τ CLtic }＝min{τ CLtoc ,τ CLtic ＞τ CLtoc }＝τ CLtoc = 75.07 years
S707, performing operation optimization control of low cycle fatigue and creep life of the valve housing and the cylinder of the nuclear turbine.
The low cycle fatigue and creep life of the weak life parts of the valve housing and the cylinder of the nuclear turbine are optimally controlled by a low cycle fatigue and creep life design monitoring method of the pressure and the thermal load of the valve housing and the cylinder of the nuclear turbine:
(1) If τ CLtc And the design monitoring of the low cycle fatigue and creep life of the weak life parts of the valve casing and the cylinder of the nuclear turbine is qualified more than or equal to 60 years, and the design monitoring of the low cycle fatigue and creep life of the weak life parts of the valve casing and the cylinder of the nuclear turbine is finished.
(2) If τ CLt In less than 60 years, the design and monitoring of the low cycle fatigue and creep life of the pressure and thermal load of the valve housing and the life weak part of the cylinder of the nuclear turbine are unqualified, which shows that materials with better mechanical performance need to be changed in the design stage, the materials are designed, the structural dimensions, the structural fillets and the like are subjected to operation optimization control improvement, and S701 to S707 are re-executed until tau CLtc And the time is more than or equal to 60 years.
For example, the low cycle fatigue and creep life of the valve housing and the weak life portion of the cylinder of the 1200MW nuclear turbine is optimally controlled.
Due to tau CLtc The design monitoring of the low cycle fatigue and creep life of the pressure and thermal load of the weak service life part of the valve casing and the cylinder of the model 1200MW nuclear turbine is qualified in the range of more than 60 years in 75.07 years, which shows that the design of the low cycle fatigue and creep life of the weak service life part of the valve casing and the cylinder of the model 1200MW nuclear turbine is in a controlled state, and the design monitoring of the low cycle fatigue and creep life design of the weak service life part of the valve casing and the cylinder of the model 1200MW nuclear turbine is finished, so that the process of running monitoring of the rotor, the valve casing and the cylinder bearing rapid start thermal stress effect life reaching 60 years can be entered.
According to the embodiment of the disclosure, the total service life of the valve casing and the cylinder is obtained, and when the total service life of the valve casing and the cylinder does not meet the monitoring qualification condition, the valve casing and the cylinder are optimally controlled to ensure that the service life of the valve casing and the cylinder of the nuclear turbine can reach the qualification condition.
In the practical application scene, when the rotor, the valve shell and the cylinder of the nuclear turbine bear the action of rapid start thermal stress, the service life of the rotor, the valve shell and the cylinder of the nuclear turbine is possibly damaged. Further, the long-life design monitoring can be performed on the rotor, the valve housing and the cylinder of the nuclear turbine bearing the rapid start thermal stress for 60 years, and as can be understood with reference to fig. 8, fig. 8 is a schematic flow chart of a method for monitoring the life of the nuclear turbine by the combined monitoring platform of the nuclear turbine according to another embodiment of the disclosure, as shown in fig. 8, the method includes:
s801, calculating thermal stress monitoring parameters of the rotor, the valve housing and the cylinder bearing rapid start thermal stress.
Based on a component model database, a load database and a material database of a nuclear turbine, inputting the metal temperature of a measuring point at the depth of 85% -95% of the wall thickness of an inner cylinder, the metal temperature of a measuring point at the depth of 85% -95% of the wall thickness of a valve casing and a cylinder, the metal temperature of a measuring point at the depth of 45% -50% of the wall thickness of the valve casing and the cylinder, and design parameters of a rotor, the valve casing and the cylinder of the nuclear turbine, a three-dimensional mechanical model and material mechanical property data, and a method and a subprogram for monitoring the rapid starting excessive thermal stress born by the rotor, the valve casing and the cylinder are used for calculating the thermal stress sigma corresponding to the service life of 60 years of the rotor of the nuclear turbine thr Thermal stress sigma corresponding to 60-year life of valve casing of nuclear turbine thv Thermal stress sigma corresponding to 60-year service life of nuclear turbine cylinder thc And rotor volume average temperature t of a nuclear turbine during start-up, shut-down or operation mi Is a simulation value of (a).
For example, for a 1200MW nuclear turbine of a certain model, based on a component model database, a load database and a material database of the nuclear turbine, the metal temperature of a measuring point at a depth of 85% -95% of the wall thickness of an inner cylinder, the metal temperature of a measuring point at a depth of 85% -95% of the wall thickness of a valve shell and a cylinder, the metal temperature of a measuring point at a depth of 45% -50% of the wall thickness of the valve shell and the cylinder, design parameters of a rotor, the valve shell and the cylinder of the nuclear turbine, a three-dimensional mechanical model and material mechanical property data are input, and a method for monitoring the rapid starting excessive thermal stress of the rotor, the valve shell and the cylinder is used for calculating the thermal stress sigma corresponding to the 60-year service life of the rotor of the 1200MW nuclear turbine of the model thr Thermal stress sigma corresponding to 60-year life of valve casing of nuclear turbine thv Thermal stress sigma corresponding to 60 years life of nuclear turbine cylinder thc Simulation value t of rotor volume average temperature of nuclear turbine during start-up, shutdown or operation mi ＝100℃。
S802, calculating the average temperature difference of the rotor volume of the nuclear turbine on line.
According to the online monitoring value of the metal temperature of the inner cylinder of the nuclear turbine, online calculating the average temperature difference delta t of the rotor volume of the nuclear turbine mr The calculation is carried out according to the following formula:
Δt mr ＝|t mi -t 95 |
wherein t is mi To simulate the rotor volume average temperature during starting, t 95 The metal temperature is measured at the depth of 85% -95% of the wall thickness of the inner cylinder of the nuclear turbine.
For example, the online monitoring value t of the metal temperature of the inner cylinder of the 1200MW nuclear turbine 95 =270 ℃, and online calculating the average temperature difference delta t of the rotor volume of the 1200MW nuclear turbine mr The calculation is carried out according to the following formula:
Δt mr ＝|t mi -t 95 |＝|100-270|＝170℃
in the above formula, t mi For a simulation value of the rotor volume average temperature during start-up of 100 ℃, t 95 The metal temperature of the measuring point at the depth of 85% -95% of the inner cylinder wall thickness of the nuclear turbine is measured, and the metal temperature of the measuring point at the depth of 95% of the inner cylinder wall thickness is 270 ℃ in the embodiment.
S803, calculating the average temperature difference of the valve casing volume of the nuclear turbine on line.
According to the online monitoring value of the metal temperature of the valve casing of the steam turbine inlet valve, the online calculation of the average temperature difference delta t of the valve casing volume of the steam turbine mv The calculation is carried out according to the following formula:
Δt mv ＝|t 50v -t 95v |
for example, the metal temperature on-line monitoring value t of the valve casing of the 1200MW nuclear turbine 95 =271 ℃ and t 50 ＝138℃On-line calculation of valve casing volume average temperature difference delta t of 1200MW nuclear turbine mv The calculation is carried out according to the following formula:
Δt mv ＝|t 50v -t 95v |＝|138-271|＝133℃
in the above formula, t 50v For the metal temperature of the measuring point at the depth of 45% -50% of the wall thickness of the valve shell, the metal temperature of the measuring point at the depth of 50% of the wall thickness of the valve shell is 138 ℃ and t is taken in the embodiment 95v The metal temperature of the measuring point at the depth of 85% -95% of the wall thickness of the valve shell is taken as 271 ℃ in the embodiment.
S804, calculating the average temperature difference of the cylinder volume of the nuclear turbine on line.
According to the on-line monitoring value of the metal temperature of the cylinder of the nuclear turbine, the average temperature difference delta t of the cylinder volume of the nuclear turbine is calculated on line mc The calculation is carried out according to the following formula:
Δt mc ＝|t 50c -t 95c |
for example, the metal temperature on-line monitoring value t of the cylinder of the 1200MW nuclear turbine 95 =240 ℃ and t 50 On-line calculation of cylinder volume average temperature difference delta t of 1200MW nuclear turbine of model number 130 DEG C mc The calculation is carried out according to the following formula:
Δt mc ＝|t 50c -t 95c |＝|130-240|＝110℃
in the above formula, t 50c The metal temperature of the measuring point at the depth of 45-50% of the wall thickness of the cylinder is taken as 130 ℃ and t is taken as the metal temperature of the measuring point at the depth of 50% of the wall thickness of the cylinder 95c The metal temperature of the measuring point at the depth of 85% -95% of the wall thickness of the cylinder is measured, and the metal temperature of the measuring point at the depth of 95% of the wall thickness of the cylinder is measured to be 240 ℃ in the embodiment.
S805, calculating the temperature difference ratio of the nuclear turbine rotor on line.
Rotor temperature difference ratio R of nuclear turbine Δtr The calculation is carried out according to the following formula:
wherein Δt is mr For the rotor volume average temperature difference, E is the elastic modulus of the rotor material at the working temperature, beta is the elastic modulus of the rotor material at the working temperature, mu is the Poisson's ratio of the rotor material at the working temperature, sigma thr The heat stress of the nuclear turbine rotor is corresponding to 60 years of service life.
For example, the model 1200MW nuclear turbine rotor temperature difference ratio R Δtr The calculation is carried out according to the following formula:
in the above formula, Δt mr The average temperature difference of the rotor volume is 170 ℃, E is the elastic modulus of the rotor material at the working temperature of 1.912 multiplied by 10 5 MPa, beta is the linear expansion coefficient of the rotor material at the working temperature of 12.62 multiplied by 10 -6 (1/K), μ is Poisson's ratio 0.303, σ of the rotor material at the operating temperature thr The thermal stress of 692Mpa corresponding to the service life of 60 years of the nuclear turbine rotor.
S806, calculating the valve casing temperature difference ratio of the nuclear turbine on line.
Valve casing temperature difference ratio R of nuclear turbine Δtv The calculation is carried out according to the following formula:
wherein Δt is mv The average temperature difference of the valve shell volume is E is the elastic modulus of the valve shell material at the working temperature, beta is the elastic modulus of the valve shell material at the working temperature, mu is the Poisson ratio of the valve shell material at the working temperature, sigma thv The valve housing of the nuclear turbine is corresponding to the thermal stress of 60 years.
For example, the valve casing temperature difference ratio R of the 1200MW nuclear turbine Δtv The calculation is carried out according to the following formula:
in the above formula, Δt mv The average temperature difference of the valve shell volume is 133 ℃, E is the elastic modulus 1.994 multiplied by 10 of the valve shell material at the working temperature 5 MPa, beta is the linear expansion coefficient of the valve casing material at the working temperature of 12.71 multiplied by 10 -6 (1/K), μ is Poisson's ratio 0.28, σ of the valve housing material at operating temperature thv The thermal stress of 458Mpa corresponding to the service life of 60 years of the valve housing of the nuclear turbine.
S807, calculating the temperature difference ratio of the cylinder of the nuclear turbine on line.
Cylinder temperature difference ratio R of nuclear turbine Δtc The calculation is carried out according to the following formula:
wherein Δt is mc For the average temperature difference of the cylinder volume, E is the elastic modulus of the cylinder material at the working temperature, beta is the elastic modulus of the cylinder material at the working temperature, mu is the Poisson's ratio of the cylinder material at the working temperature, sigma thc The thermal stress of the cylinder of the nuclear turbine corresponds to the service life of 60 years.
For example, the cylinder temperature difference ratio R of the 1200MW nuclear turbine Δtc The calculation is carried out according to the following formula:
in the above formula, Δt mc The average temperature difference of the cylinder volume is 110 ℃, E is the elastic modulus of the cylinder material at the working temperature of 1.974 multiplied by 10 5 MPa, beta is the linear expansion coefficient of the cylinder material at the working temperature of 13.00 multiplied by 10 -6 (1/K), μ is Poisson's ratio 0.28, σ of the cylinder material at operating temperature thc The thermal stress of the cylinder of the nuclear turbine is 463Mpa which corresponds to the service life of 60 years.
S808, determining the maximum temperature difference ratio of the nuclear turbine.
Maximum temperature difference ratio R of nuclear turbine Δtmax According to the following general formulaAnd (3) calculating the formula:
R Δtmax ＝{R Δtr ,R Δtv ,R Δtc }
for example, the maximum temperature difference ratio R of the 1200MW nuclear turbine Δtmax The calculation is carried out according to the following formula:
R Δtmax ＝{R Δtr ,R Δtv ,R Δtc }＝{0.885，1.022，0.847}＝1.022
s809, performing life operation optimization control of the rotor, the valve housing and the cylinder under the action of rapid start thermal stress.
By a service life monitoring method for bearing the action of rapid starting thermal stress on a nuclear turbine rotor, a valve shell and a cylinder, the service life of bearing the action of rapid starting excessive thermal stress on the nuclear turbine rotor, the valve shell and the cylinder is optimally controlled:
(1) If R is Δtmax And less than 1, the service lives of the rotor, the valve shell and the cylinder of the nuclear turbine bear the effect of the rapid start thermal stress are monitored to be qualified, which shows that the service lives of the rotor, the valve shell and the cylinder bear the effect of the rapid start thermal stress are in a controlled state.
(2) If R is Δtmax 1 or more, the life monitoring of the rotor, the valve shell and the cylinder of the nuclear turbine bearing the rapid start thermal stress is unqualified, which indicates that the starting process of the nuclear turbine is required to be optimized and improved in the operation stage, the change rate of the inlet steam temperature of the nuclear turbine is reduced to 0.5-0.8 times currently, and S801 to S808 are re-executed until R is reached Δtmax And < 1.
For example, the service lives of the rotor, the valve housing and the cylinder of the 1200MW nuclear turbine are subjected to rapid start excessive thermal stress for operation optimization control:
due to R Δtmax 1 or more, the service life monitoring of the rotor, the valve shell and the cylinder of the model 1200MW nuclear turbine bearing the effect of rapid start thermal stress is unqualified, which shows that the start process of the model 1200MW nuclear turbine is required to be optimized and improved in the operation stage, the change rate of the steam inlet temperature of the model 1200MW nuclear turbine is reduced to 0.6 times currently, S801 to S808 are executed again, and the monitoring result is shown in 7; at this time R Δtmax And less than 1, the service lives of the rotor, the valve housing and the cylinder of the 1200MW nuclear turbine bear the effect of the rapid start thermal stress are monitored to be qualified, which shows that the service lives of the rotor, the valve housing and the cylinder bear the effect of the rapid start thermal stress are in a controlled state.
Table 7 operation monitoring of a nuclear turbine subjected to rapid start thermal stress
According to the embodiment of the disclosure, the maximum temperature difference ratio of the nuclear turbine is obtained, and when the temperature difference ratio does not meet the monitoring qualified condition, the starting process is operated and optimally controlled, so that the temperature difference ratio of the nuclear turbine is reduced, and the service life of the nuclear turbine can reach the qualified condition.
The combined monitoring platform for the nuclear turbine provided by the disclosure can realize safety monitoring of the nuclear turbine, and can be further understood with reference to fig. 9, fig. 9 is a schematic flow chart of a monitoring method for the combined monitoring platform for the nuclear turbine according to another embodiment of the disclosure, as shown in fig. 9, the method includes:
and S901, when the monitoring instruction is a safety monitoring instruction, acquiring running state data and load data matched with the safety monitoring instruction and material performance data.
In the embodiment of the disclosure, the combined monitoring platform of the nuclear turbine can receive the monitoring instruction, wherein the monitoring instruction can be a safety monitoring instruction aiming at the nuclear turbine, and the combined monitoring platform of the nuclear turbine can perform safety monitoring on the nuclear turbine according to the received safety monitoring instruction.
Further, the safety monitoring instruction can be received through a data processing server of the combined monitoring platform of the nuclear turbine, and matched safety monitoring data can be obtained according to the safety monitoring instruction.
In the implementation, the safety of the nuclear turbine is greatly related to the running state, the load born and the material performance of the nuclear turbine, so that the safety monitoring data matched with the safety monitoring instruction can be determined by acquiring corresponding running state data, load data and material performance data.
The data processing server can acquire the running state data and the load data matched with the safety monitoring instruction and the material performance data from a database connected with the data processing server.
S902, based on the running state data and the load data matched with the security monitoring instruction, and the material performance data, acquiring at least one of the following data:
acquiring first intensity safety monitoring data of the nuclear turbine subjected to scaling, abrasion, corrosion and water erosion damage, which lead to power reduction and stress corrosion;
acquiring second intensity security monitoring data of a steady state and a transient state of a rotor of the nuclear turbine under the action of centrifugal force and thermal load;
acquiring third intensity security monitoring data of steady state and transient state of a valve housing and a cylinder of the nuclear turbine under the action of pressure and thermal load;
acquiring safety design monitoring data and safety operation monitoring data of a split surface of a flange under the action of bearing load, thermal load and bolt pretightening force load of a cylinder of a nuclear turbine;
and determining the first intensity security monitoring data, the second intensity security monitoring data, the third intensity security monitoring data, the security design monitoring data and the security operation monitoring data as security monitoring data of the nuclear turbine.
In the operation process of the nuclear turbine, a part of components exist, and the operation state, the bearing load action, the material performance and other relevant attribute parameters of the components are greatly related to the safe operation of the nuclear turbine.
Accordingly, the data processing server may acquire at least one of the running state data, the load data, and the material property data matched with the security monitoring instruction as the corresponding security monitoring data based on the security monitoring instruction.
Optionally, first intensity security monitoring data of the nuclear turbine subjected to scaling, abrasion, corrosion and water erosion damage resulting in power reduction and stress corrosion is obtained.
In the embodiment of the disclosure, the operation process of the nuclear turbine may be subjected to scaling, abrasion, corrosion and water erosion damage, so that the power of the nuclear turbine is reduced and stress corrosion is possible.
Therefore, the data processing server can acquire at least one of running state data, load data and material performance data matched with the state of the nuclear turbine bearing scaling, abrasion, corrosion and water erosion damage from a database connected with the data processing server, and the running state data, the load data and the material performance data are used as safety monitoring data matched with the safety monitoring instruction and are determined to be first-intensity safety monitoring data of the nuclear turbine.
Optionally, second intensity security monitoring data of a steady state and a transient state of a rotor of the nuclear turbine under the action of centrifugal force and thermal load are obtained.
In the embodiment of the disclosure, the steady state and the transient state of the rotor of the nuclear turbine have a certain influence on the safe operation of the nuclear turbine. The safety of the steady state and the transient state of the rotor can be represented by the steady state strength and the transient state strength of the rotor.
In the implementation, when the rotor of the nuclear turbine bears centrifugal force and thermal load, the steady-state strength and the transient strength of the rotor are possibly damaged. Thus, safety monitoring of the rotor may be achieved by analysis of its steady state and transient intensity data.
Further, steady-state strength data and transient strength data of the rotor of the nuclear turbine when subjected to centrifugal force and thermal load can be acquired, and determined as second strength safety monitoring data.
Optionally, third intensity security monitoring data of steady state and transient state of valve housing and cylinder of the nuclear turbine bearing pressure and thermal load are obtained.
In the embodiment of the disclosure, a certain correlation exists between the valve housing and the cylinder of the nuclear turbine and the safe operation of the nuclear turbine, wherein the safety of the valve housing and the cylinder can be represented by the transient strength and the steady-state strength of the valve housing and the cylinder.
During operation of a nuclear turbine, the valve housing and the cylinder may be subject to pressure and thermal loads. Accordingly, the safety of the valve housing and the cylinder is affected to some extent when they are subjected to pressure and thermal loads. This in turn results in the possibility of the valve housing and cylinder changing in transient and steady state strength when subjected to pressure and thermal loads.
Further, steady state and transient state strength data of the valve housing and the cylinder when subjected to pressure and thermal load may be obtained and determined as third strength safety monitoring data.
Optionally, safety design monitoring data and safety operation monitoring data of the split surface of the flange under the action of the bearing load, the thermal load and the bolt pretightening force load of the cylinder of the nuclear turbine are obtained.
In the implementation, the related state of the flange middle division surface of the cylinder of the nuclear turbine has a certain influence on the safe operation of the nuclear turbine. In this case, if the tightness of the flange center surface of the cylinder is impaired, steam leakage may occur at the flange center surface.
The relevant state of the flange split surface can be affected to a certain extent when the cylinder bears load, thermal load and bolt pretightening force load.
Therefore, the relevant data of tightness of the split surface of the cylinder flange can be obtained as corresponding monitoring data when the cylinder bearing load, the thermal load and the bolt pretightening force load of the nuclear turbine act.
Alternatively, tightness of the cylinder flange middle facets may be embodied based on the safety design data and the safety operation data of the cylinder flange middle facets, and thus the safety design data and the safety operation data of the cylinder flange middle facets may be used as the monitoring data matched with the safety monitoring instructions.
Further, when the cylinder bearing load, the thermal load and the bolt pretightening force load of the nuclear turbine act, the safety design data and the safety operation data of the middle split surface of the cylinder flange are determined to be the safety design monitoring data and the safety operation monitoring data.
Optionally, the first intensity security monitoring data, the second intensity security monitoring data, the third intensity security monitoring data, the security design monitoring data and the security operation monitoring data are determined to be security monitoring data of the nuclear turbine.
In the embodiment of the disclosure, the first intensity security monitoring data, the second intensity security monitoring data, the third intensity security monitoring data, the security design monitoring data and the security operation monitoring data are used for realizing coverage on security monitoring requirements of the nuclear turbine.
Therefore, the first intensity security monitoring data, the second intensity security monitoring data, the third intensity security monitoring data, the security design monitoring data and the security operation monitoring data can be determined as the security monitoring data of the nuclear turbine.
According to the combined monitoring platform of the nuclear turbine, safety monitoring is conducted on the nuclear turbine according to the obtained monitoring data, at least one of first-intensity safety monitoring data, second-intensity safety monitoring data, third-intensity safety monitoring data, safety design monitoring data and safety operation monitoring data corresponding to the nuclear turbine are obtained from a corresponding database, and then safety monitoring data of the nuclear turbine matched with safety monitoring instructions are determined. In the method, safety monitoring of the steam turbine is achieved through the safety monitoring data, the safety monitoring effect of the nuclear turbine is optimized, and high safety monitoring of the nuclear turbine is achieved.
In order to better understand the implementation of the safety monitoring of the nuclear turbine by the combined monitoring platform of the nuclear turbine and the optimization and improvement strategy of the nuclear turbine determined based on the safety monitoring result in the above embodiment, the following embodiment may be further combined.
In the practical application scene, when the nuclear turbine bears the effects of scaling, abrasion, corrosion and water erosion, the power is reduced and the stress corrosion is possible. Further, safety design monitoring can be performed on power reduction and stress corrosion strength of the nuclear turbine subjected to scaling, abrasion, corrosion and water erosion damage, as can be understood with reference to fig. 10, fig. 10 is a schematic flow diagram of a method for monitoring safety of the nuclear turbine by the combined monitoring platform of the nuclear turbine according to an embodiment of the disclosure, as shown in fig. 10, and the method includes:
s1001, calculating the flow ratio of the nuclear turbine.
Inputting the inlet pressure, inlet temperature and outlet pressure of the newly designed nuclear turbine, and putting the inlet pressure, inlet temperature, outlet pressure and the same working speed n of the nuclear turbine into operation 0 The method comprises the steps of (1) calculating isentropic enthalpy drop H of rated working conditions of a newly designed nuclear turbine by using a method and a subroutine for safely designing and monitoring power drop and stress corrosion intensity which bear scaling, abrasion and corrosion damage based on thermal parameters of the nuclear turbine under the conditions of different steam inlet parameters and the same working speed, wherein the steam inlet parameters and the steam outlet pressure of the nuclear turbine are 1500r/min s1 Isentropic enthalpy drop H with rated working condition of already put into operation nuclear turbine s01 Electric power N of nuclear turbine e With flow G, isentropic enthalpy drop H s Relative internal efficiency eta of steam turbine 0i Mechanical efficiency eta m Efficiency eta of generator g The relation between them is N e ＝G×H s1 ×η 0i ×η m ×η g In relative internal efficiency eta 0i Mechanical efficiency eta m And generator efficiency eta g Same and electric power N e Under the condition that the difference is within 50%, the flow G of the nuclear turbine is newly designed 1 Flow G of already put into operation nuclear turbine 01 Flow ratio F of (2) R1 The calculation formula of (2) is as follows:
wherein G is 1 G, for newly designing flow rate of rated working condition of nuclear turbine 01 The flow of rated working conditions of the put-into-operation nuclear turbine with the electric power within 50 percent is N e1 The rated working condition of the nuclear turbine is designed newly, N e01 For the electric power of rated working condition of the put-into-operation nuclear turbine, P cf Power reduction coefficient, preferably P, for new design of nuclear turbines to withstand fouling, wear and corrosion damage cf ＝1.01～1.03。
For example, the inlet pressure p of the 1200MW nuclear turbine of the model is input 01 =6.45 MPa, inlet temperature t 01 = 280.3 ℃ and exhaust pressure p k1 =5.78 kPa, already put into operation 1087MW nuclear turbine inlet pressure p 0 =6.45 MPa, inlet temperature t 0 Steam exhaust pressure p at 280.3 =deg.C k =5.78 kPa and the same operating speed n 0 Based on the thermal parameters of the 1200MW nuclear turbine model, the isentropic enthalpy drop H of the rated working condition of the 1200MW nuclear turbine is calculated by using a method and a subroutine for monitoring the power drop and stress corrosion intensity safety design which bear scaling, abrasion and corrosion damage s1 Isentropic enthalpy drop H of = 950.90kJ/kg for rated operating conditions of 1087MW nuclear turbine already put into operation s01 = 952.28kJ/kg. Electric power N of nuclear turbine e With flow G, isentropic enthalpy drop H s Relative internal efficiency eta of steam turbine 0i Mechanical efficiency eta m Efficiency eta of generator g The relation between them is N e ＝G×H s1 ×η 0i ×η m ×η g In relative internal efficiency eta 0i Mechanical efficiency eta m And generator efficiency eta g Same and electric power N e Under the condition that the difference is within 50%, the flow G of the 1200MW nuclear turbine is newly designed 1 Flow G of 1087MW nuclear turbine put into operation 01 Flow ratio F of (2) R1 The calculation formula of (2) is as follows:
in the above formula, G 1 The flow of the rated working condition of the 1200MW nuclear turbine is newly designed, G 01 For the flow rate of rated working conditions of the 1087MW nuclear turbine which is put into operation, the electric power is different by (1200-1087)/1087=10.4%<50％，N e1 The electric power of 1200MW and N for newly designing the rated working condition of the nuclear turbine e01 For the rated working condition of the nuclear turbine, the electric power 1087MW and P are cf Power reduction coefficient, preferably P, for new design of nuclear turbines to withstand fouling, wear and corrosion damage cf =1.01 to 1.03, P is taken in this example cf ＝1.02。
S1002, determining the flow of the nuclear turbine.
All-level flow G of rated working condition of already put into operation nuclear turbine with electric power within 50% 0i In order to ensure the power of the nuclear turbine, the flow G of each stage of the nuclear turbine i The calculation formula of (2) is as follows:
G i ＝G 0i ×F R1
wherein F is R1 Is the flow ratio of the nuclear turbine.
For example, the flow G of each stage of rated working condition of the 1087MW nuclear turbine which has been put into operation and has electric power within 50% of the existing electric power 0i In order to ensure the power of the newly designed 1200MW nuclear turbine, the flow G of each stage of the 1200MW nuclear turbine i The calculation formula of (2) is as follows:
G i ＝G 0i ×F R1 ＝1.127669G 0i
in the above formula, F R1 Is the flow ratio of the nuclear turbine.
S1003, determining the modeling ratio of the nuclear turbine.
Flow ratio F of known nuclear turbine R1 Modeling ratio S of nuclear turbine F The calculation formula of (2) is as follows:
for example, the flow ratio F of a known 1200MW nuclear turbine R1 The modeling ratio S of the 1200MW nuclear turbine F The calculation formula of (2) is as follows:
s1004, modeling and amplifying the size of the nuclear turbine component.
The structural design of the nuclear turbine adopts a modeling design method on the basis of the already put into operation of the nuclear turbine, and the main structural size of the already put into operation of the nuclear turbine with the existing electric power within 50 percent is multiplied by the modeling ratio S of the nuclear turbine F And obtaining the main structural dimension of the newly designed nuclear turbine.
For example, the structural design of the model 1200MW nuclear turbine adopts a modeling design method on the basis of the already put into operation 1087MW nuclear turbine, and the main structural size of the already put into operation 1087MW nuclear turbine with the existing electric power within 50% is multiplied by the modeling ratio S of the model 1200MW nuclear turbine F The main structural dimension of the newly designed 1200MW nuclear turbine is obtained.
S1005, calculating the safety design amount of stress corrosion damage of the rotor and the blade root of the nuclear turbine.
Inputting design parameters and a three-dimensional mechanical model of a nuclear turbine rotor and a blade root, centrifugal force and thermal load of the nuclear turbine rotor and the blade root, and material performance data, and calculating the maximum main stress sigma of the surface of the nuclear turbine rotor or the blade root, which contacts wet steam, under steady-state rated working conditions by using a method and a subroutine for safely designing and monitoring the power reduction and stress corrosion intensity which bear scaling, abrasion, corrosion and water erosion damage 1 Invoking yield limit of material at working temperature t in material database
For example, design parameters and a three-dimensional mechanical model of a rotor and a blade root of the model 1200MW nuclear turbine, centrifugal force and thermal load of the rotor and the blade root of the nuclear turbine, and material performance data are input, and a maximum principal stress sigma of a blade root groove contact wet steam surface of the rotor blade root groove of the model 1200MW nuclear turbine under steady-state rated working conditions is calculated by using a method and a subprogram for safely designing and monitoring power reduction and stress corrosion intensity which bear scaling, abrasion, corrosion and water erosion damage 1 =432 MPa, invoking the yield limit of the rotor material at the working temperature t=100 ℃ in the material database
S1006, calculating the maximum principal stress ratio of the rotor and the blade root of the nuclear turbine under the steady-state rated working condition.
Maximum main stress ratio R of surface of contact wet steam of nuclear turbine rotor and blade root under steady-state rated working condition σ1 The calculation is carried out according to the following formula:
wherein sigma 1 The maximum principal stress of the wet steam contact surface of the rotor or the blade root of the nuclear turbine under the steady-state rated working condition,
is the yield limit of the material at the operating temperature.
For example, the maximum main stress ratio R of the surface of the wet steam contacted with the rotor and the blade root of the 1200MW nuclear turbine under steady-state rated working condition σ1 The calculation is carried out according to the following formula:
in the above, σ 1 Is steady-state rated conditionThe maximum main stress of the surface of the rotor or the blade root of the nuclear turbine, which contacts the wet steam, is 432MPa,
is the yield limit 640MPa of the rotor material at the working temperature of 100 ℃.
S1007, running optimization control of stress corrosion intensity of the rotor and the blade root of the nuclear turbine.
The method for safely designing and monitoring the power reduction and the stress corrosion intensity of the nuclear turbine subjected to scaling, abrasion and corrosion damage is used for optimally controlling the operation of the stress corrosion intensity of the rotor and the blade root of the nuclear turbine:
(1) If R is σ1 <And 0.7, the safety design monitoring of the stress corrosion damage of the nuclear turbine rotor and the blade root is qualified, which shows that the stress corrosion damage of the nuclear turbine rotor and the blade root is in a controlled state, and the design monitoring of the stress corrosion damage of the nuclear turbine rotor and the blade root is finished.
(2) If R is σ1 Not less than 0.7, unqualified safety design monitoring of stress corrosion damage of the rotor and the blade root of the nuclear turbine, which indicates that materials with better mechanical properties need to be changed in the design stage, the materials are subjected to operation optimization control improvement on the design, the structural size, the wall thickness, the structural fillets and the like, and S1005 to S1007 are re-executed until R is reached σ1 <0.7;
by way of example, the stress corrosion intensity of the model 1200MW nuclear turbine rotor and the blade root is optimally controlled by a design monitoring method of the safety of the stress corrosion damage of the nuclear turbine rotor and the blade root.
Due to R σ1 ＝0.675<And 0.7, the safety design monitoring of the stress corrosion damage of the model 1200MW nuclear turbine rotor and the blade root is qualified, which shows that the stress corrosion damage of the model 1200MW nuclear turbine rotor and the blade root is in a controlled state, and the design monitoring of the stress corrosion damage of the model 1200MW nuclear turbine rotor and the blade root is finished.
In the embodiment of the disclosure, the maximum main stress ratio of the rotor and the blade root of the nuclear turbine in the steady-state rated working condition meets the monitoring qualification condition, which indicates that the stress corrosion damage of the rotor and the blade root of the nuclear turbine is in a controlled state, and the safe operation of the nuclear turbine is ensured.
In practical application, the tightness of the middle surface of the flange of the cylinder of the nuclear turbine can be affected when the cylinder bears the load of force, heat load and bolt pretightening force. The safety design monitoring can be performed on the tightness of the split surface of the cylinder of the nuclear turbine in the flange bearing the load of the force, the heat load and the bolt pretightening force, and can be understood with reference to fig. 11, fig. 11 is a schematic flow chart of a safety monitoring method of the nuclear turbine by the combined monitoring platform of the nuclear turbine according to another embodiment of the disclosure, as shown in fig. 11, the method includes:
s1101, calculating the tightness setting amount of the middle surface of the cylinder flange.
Based on a component model database, a load database and a material database of the nuclear turbine, inputting design parameters and a three-dimensional mechanical model of a cylinder of the nuclear turbine, pressure and heat load of the cylinder and bolt preload, and material performance data, and calculating a maximum opening penetration gap c of a flange center section of the cylinder of the nuclear turbine by using a method and a subprogram for tightness design monitoring of the flange center section under the actions of the load of the cylinder, the heat load and the bolt preload op (mm) minimum contact stress sigma of flange bisection surface of cylinder cs 。
For example, based on a component model database, a load database and a material database of a nuclear turbine, design parameters and a three-dimensional mechanical model of a cylinder of the type 1200MW nuclear turbine, pressure and heat load of the cylinder and bolt pretightening force load, and material performance data are input, a method and a subroutine for monitoring the flange middle-split tightness design of the cylinder are used, a single-layer cylinder is adopted for a high-pressure cylinder of the type 1200MW nuclear turbine, and a flange middle-split maximum opening penetration gap c of the type 1200MW nuclear turbine cylinder is calculated op =0.03 mm and flange median plane minimum contact stress σ for cylinder cs ＝14.51MPa。
S1102, calculating the pressure difference between the inner surface and the outer surface of the middle division surface of the flange of the cylinder of the nuclear turbine.
The differential pressure delta P between the inner surface and the outer surface of the flange middle division surface of the cylinder of the nuclear turbine is calculated according to the following formula:
ΔP＝P i -P o
wherein P is i Maximum vapor pressure for cylinder inner surface, P o Cylinder outer surface fluid pressure.
For example, the differential pressure Δp between the inner and outer surfaces of the flange median plane of the cylinder of the nuclear turbine is calculated according to the following formula:
ΔP＝P i -P o ＝6.45-0.10＝6.35MPa
in the above formula, P i Is the maximum steam pressure of the inner surface of the cylinder of 6.45MPa, P o The atmospheric pressure of the outer surface of the cylinder is 0.10MPa.
S1103, calculating the ratio of the penetration gap of the split surface opening of the flange of the cylinder of the nuclear turbine.
Flange split surface opening penetration gap ratio R of nuclear turbine cylinder cop The calculation is carried out according to the following formula:
wherein c op The gap is penetrated by a flange split surface opening of the cylinder of the nuclear turbine.
For example, the flange center-split opening penetration gap ratio R of the model 1200MW nuclear turbine cylinder cop The calculation is carried out according to the following formula:
s1104, calculating the ratio of the contact stress of the middle part surface of the flange of the cylinder of the nuclear turbine.
Flange split surface contact stress ratio R of nuclear turbine cylinder σcs The calculation is carried out according to the following formula:
wherein sigma cs The pressure difference is the flange center-to-center surface contact stress of the cylinder of the nuclear turbine, and delta P is the pressure difference between the inner surface and the outer surface of the cylinder of the nuclear turbine.
For example, the flange center-to-side contact stress ratio R of the model 1200MW nuclear turbine cylinder σcs The calculation is carried out according to the following formula:
s1105, performing operation optimization control on split surface opening of a flange of a cylinder of the nuclear turbine.
The flange center-split opening of the nuclear turbine cylinder is optimally controlled by a flange center-split tightness design monitoring method under the actions of bearing load, thermal load and bolt pretightening force load of the nuclear turbine cylinder:
(1) If R is cop And (2) the design and monitoring of the flange center opening of the nuclear turbine cylinder are qualified, and the design and monitoring of the flange center opening of the nuclear turbine cylinder is finished.
(2) If R is cop Not less than 1, unqualified design and monitoring of the flange split opening of the cylinder of the nuclear turbine, which indicates that the operation optimization control improvement of flange size, bolt number, bolt diameter, bolt material, bolt pretightening force and the like is required in the design stage, and the steps S1101 to S1105 are re-executed until R is reached cop And < 1.
For example, the flange center section opening of the 1200MW nuclear turbine cylinder is optimally controlled by a flange center section tightness design monitoring method under the actions of bearing load, heat load and bolt pretightening force load of the nuclear turbine cylinder.
Due to R cop The design and the monitoring of the flange split surface opening of the model 1200MW nuclear turbine cylinder are qualified, which is shown that the flange split surface opening of the nuclear turbine cylinder is in a controlled state, and the model is shown in the specificationAnd (5) finishing the design monitoring of the split surface opening of the flange of the 1200MW nuclear turbine cylinder.
S1106, operation optimization control of the flange center-to-surface contact stress of the nuclear turbine cylinder.
The flange center-to-center surface contact stress of the nuclear turbine cylinder is optimally controlled by a flange center-to-center surface tightness design monitoring method under the actions of bearing load, thermal load and bolt pretightening force load of the nuclear turbine cylinder:
(1) If R is σcs And the design monitoring of the flange center-to-surface contact stress of the cylinder of the nuclear turbine is qualified and is more than 1.25, which indicates that the flange center-to-surface contact stress of the cylinder is in a controlled state and the design monitoring of the flange center-to-surface contact stress of the cylinder of the nuclear turbine is finished.
(2) If R is σcs Failure in design and monitoring of the surface contact stress of the flange of the cylinder of the nuclear turbine is less than or equal to 1, which indicates that the operation optimization control improvement of the flange size, the number of bolts, the bolt diameter, the bolt material, the bolt pretightening force and the like is required in the design stage, and S1101 to S1106 are re-executed until R is reached σcs > 1.25.
For example, the flange center-to-center contact stress of the 1200MW nuclear turbine cylinder is optimally controlled by a flange center-to-center tightness design monitoring method under the actions of bearing load, heat load and bolt pretightening force load of the nuclear turbine cylinder.
In view of R σcs The design and monitoring of the flange center-to-surface contact stress of the model 1200MW nuclear turbine cylinder are qualified, and the design and monitoring of the flange center-to-surface contact stress of the model 1200MW nuclear turbine cylinder is finished.
In the embodiment of the disclosure, the flange center opening penetration gap ratio and the contact stress ratio of the cylinder meet the monitoring qualification conditions, which indicate that the flange center opening and the contact stress of the cylinder of the nuclear turbine are in a controlled state, and ensure the safe operation of the nuclear turbine.
In practical application, the stability and transient safety of the valve housing and the cylinder of the nuclear turbine may be affected when the valve housing and the cylinder bear pressure and thermal load. The safety design monitoring can be performed on the steady-state and transient-state strength of the valve housing and the cylinder of the nuclear turbine bearing the pressure and the thermal load, and as can be understood with reference to fig. 12, fig. 12 is a schematic flow chart of a safety monitoring method of the nuclear turbine by the combined monitoring platform of the nuclear turbine according to another embodiment of the disclosure, as shown in fig. 12, the method includes:
s1201, calculating steady-state and transient-state strength safety design quantities of a valve housing and a cylinder of the nuclear turbine.
The method comprises the steps of adopting a component model database, a load database and a material database, inputting design parameters and a three-dimensional mechanical model of a valve casing and a cylinder of a nuclear turbine, a start-stop curve, a valve casing and a cylinder pressure load and a thermal load, and material performance data, determining a strength weak part with maximum transient stress by using a steady-state and transient strength design monitoring method and a subprogram of the valve casing and the cylinder bearing the pressure load and the thermal load, and calculating the surface equivalent stress (Von·Misses stress) sigma of the strength weak part of the valve casing and the cylinder of the nuclear turbine in a steady-state rated working condition e2 And operating temperature t 2 And surface equivalent stress (von mises stress) σ at transient conditions e3 And operating temperature t 3 。
For example, based on a component model database, a load database and a material database, design parameters and a three-dimensional mechanical model of a valve casing and a cylinder of the 1200MW nuclear turbine, a start-stop curve, a valve casing and a cylinder pressure load and a heat load, and material performance data are input, a method and a subroutine for steady-state and transient strength design monitoring of the valve casing and the cylinder under the action of the pressure load and the heat load are used, and a strength weak part with the largest transient stress is determined to be a blade root groove of an inner surface steam inlet side stator blade of the 1200MW nuclear turbine with larger transient stress, a blade root groove of an inner surface steam inlet side stator blade of the high-pressure inner cylinder, and a surface equivalent stress sigma of the strength weak part under steady-state rated working conditions is determined e2 =58 MPa and operating temperature t 2 Surface equivalent stress sigma at 278 ℃ and transient conditions e3 =131 MPa and operating temperature t 3 ＝194℃。
S1202, calculating the surface equivalent stress ratio of the valve housing of the nuclear turbine and the steady-state rated working condition of the cylinder.
Surface equivalent stress ratio R of valve housing and cylinder of nuclear turbine in steady-state rated working condition σe2c The calculation is carried out according to the following formula:
wherein sigma e2 Is the surface equivalent stress of the weak strength part of the valve housing and the cylinder of the nuclear turbine in the steady-state rated working condition,
at an operating temperature t 2 Yield limit of the lower material.
For example, the surface equivalent stress ratio R of the weak strength part of the valve casing and the cylinder of the 1200MW nuclear turbine in steady-state rated working condition σe2c The calculation is carried out according to the following formula:
in the above-mentioned description of the invention,
at an operating temperature t 2 Material yield limit 211MPa at 278 ℃.
S1203, calculating the surface equivalent stress ratio of the valve housing of the nuclear turbine and the transient working condition of the cylinder.
Surface equivalent stress ratio R of valve casing and cylinder of nuclear turbine in transient working condition σe3c The calculation is carried out according to the following formula:
wherein sigma e3 Is the surface equivalent stress of the weak strength part of the valve housing and the cylinder of the nuclear turbine in the transient working condition,
at an operating temperature t 3 Yield limit of the lower material.
For example, the valve casing of the 1200MW nuclear turbine and the weak strength part of the cylinder have the surface equivalent stress ratio R in the transient working condition σe3c The calculation is carried out according to the following formula:
in the above-mentioned description of the invention,
at an operating temperature t 3 Yield limit of material at 194 ℃ 214MPa.
S1204, performing operation optimization control on the valve housing and the cylinder of the nuclear turbine under steady-state rated working condition strength.
The steady-state and transient-state strength design monitoring method for bearing centrifugal force load and thermal load action of the valve housing and the cylinder of the nuclear turbine is used for carrying out operation optimization control on steady-state rated working condition strength of the valve housing and the cylinder of the nuclear turbine:
(1) If R is σe2c And the design and monitoring of the valve housing and the cylinder of the nuclear turbine in the steady-state rated working condition are qualified, and the design and monitoring of the valve housing and the cylinder of the nuclear turbine in the steady-state rated working condition are finished.
(2) If R is σe2c Not less than 1, unqualified design and monitoring of the valve casing and the cylinder of the nuclear turbine in steady-state rated working condition strength, which indicates that the operation optimization control improvement of the structure size, the structure fillet, the supporting structure, the material selection and the like is required in the design stage, and the steps from S1201 to S1204 are re-executed until R is reached σe2c Until < 1;
for example, the steady-state rated working condition intensity of the valve housing and the cylinder of the 1200MW nuclear turbine is controlled in an operation optimization mode through a steady-state and transient intensity design monitoring method that the valve housing and the cylinder of the nuclear turbine bear centrifugal force load and thermal load.
Due to R σe2c The design and the monitoring of the valve housing and the cylinder of the model 1200MW nuclear turbine are qualified in the steady-state rated working condition intensity, which is shown that the valve housing and the cylinder of the nuclear turbine are in a controlled state in the steady-state rated working condition intensity, and the design and the monitoring of the valve housing and the cylinder of the model 1200MW nuclear turbine are finished.
S1205, performing operation optimization control on the valve housing and the cylinder of the nuclear turbine under the transient working condition.
The method is characterized in that the structural strength of the valve housing and the cylinder of the nuclear turbine is optimally controlled in operation by a steady-state and transient-state strength design monitoring method for bearing the pressure load and the thermal load of the valve housing and the cylinder of the nuclear turbine:
(1) If R is σe3c The structural strength design and monitoring of the valve housing and the cylinder of the nuclear turbine under the transient working condition are qualified, which shows that the structural strength of the valve housing and the cylinder of the nuclear turbine under the transient working condition is in a controlled state, and the structural strength design and monitoring of the valve housing and the cylinder of the nuclear turbine under the transient working condition are finished;
(2) If R is σe3c Not less than 1, unqualified structural strength design and monitoring of the valve casing and the cylinder of the nuclear turbine under transient working conditions, which indicates that the operation optimization control improvement of structural dimensions, structural fillets, supporting structures, material selection and the like is required in the design stage, and S1201 to S1205 are executed until R is reached σe3c And < 1.
For example, the model 1200MW nuclear turbine valve housing and cylinder transient condition structural strength is optimally controlled by a steady state and transient state strength design monitoring method that the nuclear turbine valve housing and cylinder bear pressure load and thermal load.
Due to R σe3c The structural strength of the valve casing and the cylinder of the model 1200MW nuclear turbine is designed and monitored to be qualified under the transient working condition, which is shown that the structural strength of the valve casing and the cylinder of the nuclear turbine under the transient working condition is in a controlled state, and the model 1And (5) finishing the design monitoring of the structural strength of the valve housing and the cylinder of the 200MW nuclear turbine under the transient working condition.
In the embodiment of the disclosure, the surface equivalent stress ratio of the valve housing and the cylinder in the steady-state rated working condition and the transient working condition meets the monitoring qualification condition, which indicates that the structural strength of the valve housing and the cylinder in the steady-state rated working condition and the transient working condition of the nuclear turbine is in a controlled state, and the safe operation of the nuclear turbine is ensured.
The combined monitoring platform for the nuclear turbine provided by the disclosure can realize reliability monitoring of the nuclear turbine, and can be further understood with reference to fig. 13, and fig. 13 is a schematic flow chart of a monitoring method for the combined monitoring platform for the nuclear turbine according to another embodiment of the disclosure, as shown in fig. 13, the method includes:
s1301, when the monitoring instruction is a reliability monitoring instruction, acquiring running state data and load data matched with the reliability monitoring instruction and material performance data.
In the embodiment of the disclosure, the combined monitoring platform of the nuclear turbine can receive the monitoring instruction, wherein the monitoring instruction can be a reliability monitoring instruction aiming at the nuclear turbine, and the combined monitoring platform of the nuclear turbine can monitor the reliability of the nuclear turbine according to the received reliability monitoring instruction.
Further, the reliability monitoring instruction can be received through a data processing server in a joint monitoring platform of the nuclear turbine, and matched reliability monitoring data can be obtained according to the reliability monitoring instruction.
In the implementation, the reliability of the nuclear turbine is greatly related to the running state, the load born and the material performance of the nuclear turbine, so that the reliability monitoring data matched with the reliability monitoring instruction can be determined by acquiring corresponding running state data, load data and material performance data.
The data processing server can acquire the running state data and the load data matched with the reliability monitoring instruction and the material performance data from a database connected with the data processing server.
S1302, based on the operational status data and the load data matched with the reliability monitoring instruction, and the material property data, acquiring at least one of the following data:
acquiring dynamic strength and vibration reliability monitoring data of the action of centrifugal force, low-frequency exciting force and high-frequency exciting force borne by a moving blade of a nuclear turbine;
acquiring torsional vibration reliability monitoring data of a multi-rotor system of a nuclear turbine bearing electric disturbance faults of a power grid;
Acquiring first shafting vibration reliability monitoring data of a rotor and bearing system of a nuclear turbine, wherein the first shafting vibration reliability monitoring data bear the effects of forced vibration and self-excited vibration;
acquiring second axis system vibration reliability monitoring data of a rotor and a bearing system of the nuclear turbine under the actions of forced vibration and self-excited vibration;
and determining the dynamic intensity and vibration monitoring data, torsional vibration monitoring data, first shafting vibration reliability monitoring data and second shafting vibration reliability monitoring data as reliability monitoring data of the nuclear turbine.
In the operation process of the nuclear turbine, a part of components exist, and related attribute parameters such as the operation state, the bearing load action, the material performance and the like of the components are greatly related to the reliable operation of the nuclear turbine.
Accordingly, the data processing server may acquire at least one of the operational status data, the load data, and the material property data, which match the reliability monitoring instructions, as the corresponding reliability monitoring data based on the reliability monitoring instructions.
Optionally, the dynamic intensity and vibration reliability monitoring data of the action of the centrifugal force, the low-frequency exciting force and the high-frequency exciting force of the moving blades of the nuclear turbine are obtained.
In the operation process of the nuclear turbine, the moving blades of the nuclear turbine are likely to vibrate, wherein the relative states of the moving blades of the nuclear turbine, which bear centrifugal force, low-frequency exciting force and high-frequency exciting force, have a certain influence on the operation reliability of the nuclear turbine.
Further, the relevant data when the rotor blade of the nuclear turbine is subjected to the centrifugal force, the low-frequency excitation force and the high-frequency excitation force can be used as corresponding monitoring data, wherein the relevant data of the dynamic strength and the relevant data of the vibration can be included, and the relevant data of the dynamic strength and the relevant data of the vibration can be determined to be the monitoring data of the dynamic strength and the vibration reliability which are matched with the reliability monitoring instruction.
Optionally, torsional vibration reliability monitoring data of a multi-rotor system of the nuclear turbine bearing the power grid electrical disturbance fault are obtained.
In the operation process of the nuclear turbine, the multi-rotor system of the nuclear turbine is safe in torsion vibration bearing disturbance faults of electric appliances of a power grid, and has a certain influence on the operation reliability of the nuclear turbine.
Furthermore, the design monitoring can be carried out on the torsional vibration safety of the multi-rotor system of the nuclear turbine in bearing the disturbance fault of the electric network appliance, and the corresponding torsional vibration data are used as torsional vibration reliability monitoring data of the multi-rotor system in bearing the electric network disturbance fault.
Optionally, first shafting vibration reliability monitoring data of the rotor and bearing system of the nuclear turbine subjected to forced vibration and self-excited vibration are obtained.
During the operation of the nuclear turbine, shafting vibration may exist when the rotor and the bearing system of the nuclear turbine bear the actions of forced vibration and self-excited vibration. The shafting vibration generated by the rotor and bearing system has a certain influence on the operation reliability of the nuclear turbine.
Further, reliability monitoring of the rotor and bearing system of the nuclear turbine can be achieved through relevant operation data of the rotor and bearing system when shafting vibration occurs under the action of forced vibration and self-excited vibration.
In the embodiment of the disclosure, running state data of the rotor and the bearing system when the rotor and the bearing system bear forced vibration and self-excitation actions can be obtained and determined to be corresponding first shafting vibration reliability monitoring data, wherein the first shafting vibration reliability monitoring data can comprise a critical rotation speed ratio of the rotor and the bearing system, a destabilization rotation speed ratio of the rotor and the bearing system and the like.
Optionally, second axis vibration reliability monitoring data of the rotor and bearing system of the nuclear turbine subjected to forced vibration and self-excited vibration is obtained.
In the embodiment of the disclosure, shafting vibration generated when the rotor and the bearing system of the nuclear turbine bear the forced vibration and self-excited vibration can be monitored, and reliability monitoring of the nuclear turbine is realized based on the monitoring result corresponding to the shafting vibration.
Further, monitoring data of shafting vibration of the rotor and bearing system of the nuclear turbine subjected to the effects of forced vibration and self-excited vibration can be obtained, and the monitoring data are determined to be corresponding second shafting vibration reliability monitoring data. The second shaft system vibration reliability monitoring data can comprise a ratio of on-line monitoring of shaft vibration relative displacement of the rotor shaft journal, a ratio of on-line monitoring of vibration speed of the bearing seat and the like.
Optionally, the dynamic intensity and vibration reliability monitoring data, the torsional vibration reliability monitoring data, the first shafting vibration reliability monitoring data and the second shafting vibration reliability monitoring data are determined as the reliability monitoring data of the nuclear turbine.
In the embodiment of the disclosure, the monitoring coverage of the components influencing the running reliability of the nuclear turbine can be realized through the dynamic strength and vibration reliability monitoring data, torsional vibration reliability monitoring data, first shafting vibration reliability monitoring data and second shafting vibration reliability monitoring data.
Therefore, the dynamic intensity and vibration reliability monitoring data, the torsional vibration reliability monitoring data, the first shafting vibration reliability monitoring data and the second shafting vibration reliability monitoring data can be determined to be the reliability monitoring data of the nuclear turbine.
According to the combined monitoring platform for the nuclear turbine, reliability monitoring is conducted on the nuclear turbine according to the obtained monitoring data, at least one of dynamic intensity and vibration reliability monitoring data, torsional vibration reliability monitoring data, first shafting vibration reliability monitoring data and second shafting vibration reliability monitoring data corresponding to the nuclear turbine are obtained from a corresponding database, and further the reliability monitoring data of the nuclear turbine matched with the reliability monitoring instruction is determined. In the method, the reliability of the steam turbine is monitored through the reliability monitoring data, the reliability monitoring effect of the nuclear turbine is optimized, and the high reliability of the nuclear turbine is monitored.
In order to better understand the implementation of the reliability monitoring of the nuclear turbine by the combined monitoring platform of the nuclear turbine and the optimization and improvement strategy of the nuclear turbine determined based on the reliability monitoring result in the above embodiment, the following embodiment may be further combined.
In a practical application scenario, reliability design monitoring can be performed on dynamic strength and vibration safety of a rotor blade of a nuclear turbine subjected to centrifugal force, low-frequency exciting force and high-frequency exciting force, and as can be understood with reference to fig. 14, fig. 14 is a flow diagram of a method for monitoring reliability of the nuclear turbine by a combined monitoring platform of the nuclear turbine according to an embodiment of the disclosure, as shown in fig. 14, the method includes:
s1401, calculating running state data of the moving blade of the nuclear turbine.
Based on a component model database, a load database and a material database of the nuclear turbine, design parameters and a three-dimensional mechanical model, centrifugal force loads and exciting force loads and material mechanical property data of the moving blades of the nuclear turbine are input, and the vibration stress sigma of the moving blades of the nuclear turbine is calculated by using a method and a subprogram for monitoring the moving strength and vibration design of the moving blades subjected to the actions of centrifugal force, low-frequency exciting force and high-frequency exciting force v Vibration resistance strength sigma a Safety factor of kinetic strength permission [ S ] f ]First order vibration frequency f 1 At the maximum operating speed (1+0.01) n 0 Frequency f of vibration at the time d1 At the lowest working rotation speed (1-0.03) n 0 Frequency f of vibration at a finite time d2 M-order radial vibration frequency f of long blade connected in whole circle dm Operating speed n of a nuclear turbine 0 。
For example, a component model database and load based on a nuclear turbineThe method comprises the steps of inputting design parameters and a three-dimensional mechanical model, centrifugal force loads and exciting force loads of a moving blade of a model 1200MW nuclear turbine and material mechanical property data, calculating to obtain running state data of the moving blade of the model 1200MW nuclear turbine by using a method and a subprogram for monitoring the moving strength and vibration design of the moving blade under the actions of centrifugal force, low-frequency exciting force and high-frequency exciting force, and in the embodiment of the invention, the running state data of the moving blade comprises vibration stress sigma v =18.83 MPa, vibration resistance σ a Security factor for dynamic strength = 253.99MPa [ S ] f ]=2.45, first order vibration frequency f 1 =123 Hz at the maximum operating speed (1+0.01) n 0 Frequency f of vibration at the time d1 =128 Hz, at minimum operating speed (1-0.03) n 0 Frequency f of vibration at a finite time d2 M=6-order radial vibration frequency f of a long blade of 107Hz, full-circle connection dm Operation speed n of nuclear turbine =1186 Hz 0 ＝1500r/min＝25Hz。
S1402, calculating the dynamic strength safety ratio of the moving blade.
Dynamic strength safety ratio R of centrifugal force and steam flow exciting force born by moving blades of nuclear turbine σv The calculation is carried out according to the following formula:
in the above formula, sigma a For the vibration resistance of the rotor blade, sigma v Is the vibration stress of the moving blade [ S ] f ]Safety factors are allowed for the dynamic strength of the rotor blade.
For example, the dynamic strength safety ratio R of the type 1200MW nuclear turbine rotor blade subjected to centrifugal force and steam flow exciting force σv The calculation is carried out according to the following formula:
in the above, σ a Is a moving bladeIs 253.99MPa and sigma v The vibration stress of the rotor blade is 18.83MPa, [ S ] f ]Safety factor 2.45 is permitted for the dynamic strength of the rotor blade.
S1403, a first frequency resonance ratio is calculated for the rotor blade to avoid the low frequency excitation force.
Optionally, the first frequency resonance ratio includes a lower limit ratio and an upper limit ratio of the first order vibration frequency to avoid the low frequency excitation force frequency.
First-order vibration frequency of moving blade of nuclear turbine avoids low-frequency exciting force frequency lower limit ratio R d1 And upper limit ratio R u1 The calculation is respectively carried out according to the following formula:
In the above formula, f d1 For the rotor blade at the maximum operating speed limit (1+0.01) n 0 Frequency of vibration at time f d2 For the rotor blade at the minimum working rotation speed (1-0.03) n 0 The vibration frequency at the time, K is the rotation speed multiplying power of exciting force, n 0 Is the working speed of the nuclear turbine.
For example, the first order vibration frequency of the 1200MW nuclear turbine rotor blade avoids the lower limit ratio R of the low frequency exciting force frequency d1 And upper limit ratio R u1 The calculation is respectively carried out according to the following formula:
in the above formula, f d1 For the vibration frequency 128 of the rotor blade at the maximum operating speed limit (1+0.01) n0Hz，f d2 For the rotor blade at the minimum working rotation speed (1-0.03) n 0 Vibration frequency 107hz at the time of vibration, k=5 is the rotation speed multiplying power of exciting force, n 0 The working speed of the 1200MW nuclear turbine is 1500 r/min=25 Hz.
S1404, a second frequency resonance ratio of the rotor blade avoiding the high-frequency excitation force is calculated.
First-order vibration frequency of moving blade of nuclear turbine avoids high-frequency exciting force frequency Z n n 0 Ratio of resonance Δf h The calculation is carried out according to the following formula:
in the above formula, f 1 For the first order vibration frequency of the rotor blade, Z n For the number of stator blades, n 0 Is the working speed of the nuclear turbine.
For example, the model 1200MW nuclear turbine rotor blade has a first frequency resonance ratio Δf at which the first frequency of vibration avoids the high frequency excitation force h The calculation is carried out according to the following formula:
in the above formula, f 1 Is the first-order vibration frequency 123Hz, Z of the moving blade n For the number of stator blades 60, n 0 The working speed of the nuclear turbine is 1500 r/min=25 Hz.
S1405, calculating a third frequency resonance ratio of the m-order diameter vibration frequency of the whole circle of connecting long blades to avoid high-frequency excitation force.
The m-order diameter vibration frequency of the whole circle of connecting long blade avoids the high-frequency exciting force frequency Z n n 0 Ratio of resonance Δf m The calculation is carried out according to the following formula:
in the above formula, f dm The m-order diameter vibration frequency of the long blade is connected for the whole circle, m is the pitch diameter number of the whole circle of blade vibration, Z n Is the number of stator vanes.
For example, the m-order diameter vibration frequency of the whole circle of the connecting long blade avoids the third frequency resonance ratio Δf of the high-frequency exciting force m The calculation is carried out according to the following formula:
in the above formula, f dm The m=6-order diameter vibration frequency 1186Hz of the long blade is connected for the whole circle, m=6 is the pitch diameter number of the whole circle of blade vibration, and Z n The number of stator vanes is 60.
S1406, running optimization control of dynamic strength safety of the moving blade.
The dynamic intensity and vibration design monitoring method for the centrifugal force, the low-frequency exciting force and the high-frequency exciting force applied to the moving blades of the nuclear turbine is used for carrying out operation optimization control on the safety of the dynamic intensity of the moving blades of the nuclear turbine:
(1) If R is σv And the design and monitoring of the dynamic intensity safety of the moving blade of the nuclear turbine are qualified more than 1, which indicates that the dynamic intensity safety of the moving blade of the nuclear turbine is in a controlled state, and the design and monitoring of the vibration intensity safety of the moving blade of the nuclear turbine is finished.
(2) If R is σv The design and monitoring of dynamic strength safety of the moving blade of the nuclear turbine are unqualified, which shows that the optimization control improvement of the operation of the blade profile width and thickness, the structure fillet, the connecting structure, the thickness of the shroud, the material mark and the like of the moving blade is required in the design stage, and the steps S1401 to S1406 are re-executed until R σv > 1.
For example, through dynamic strength optimization improvement strategy, the dynamic strength safety of the moving blade of the 1200MW nuclear turbine is controlled in an operation optimization mode:
(1) If R is σv The design and monitoring of the dynamic intensity safety of the moving blade of the model 1200MW nuclear turbine are qualified, which indicates the dynamic intensity safety of the moving blade of the model 1200MW nuclear turbineIn a controlled state, the design monitoring of the vibration intensity safety of the moving blade is finished.
S1407, the moving blade avoids the operation optimization control of low-frequency exciting force frequency resonance.
The method is characterized in that by means of a dynamic strength and vibration design monitoring method for the nuclear turbine moving blades subjected to centrifugal force, low-frequency exciting force and high-frequency exciting force, operation optimization control is carried out on the nuclear turbine moving blades by avoiding low-frequency exciting force frequency resonance:
(1) If R is d1 > 5% and R u1 The design and monitoring of the nuclear turbine moving blade avoiding the low-frequency exciting force frequency resonance are qualified, and the design and monitoring that the nuclear turbine moving blade avoiding the low-frequency exciting force frequency resonance is in a controlled state is shown, and the moving blade avoiding the low-frequency exciting force frequency resonance is finished.
(2) If R is d1 Less than or equal to 5 percent or R u1 Less than or equal to 3 percent, the nuclear turbine rotor blade avoids the disqualification of low-frequency exciting force frequency resonance design monitoring, which indicates that the optimization control improvement of the operation of the blade profile width and thickness, the structure fillet, the connecting structure, the shroud thickness, the material mark and the like of the rotor blade is required in the design stage, and the S1401 to S1407 are re-executed until R is reached d1 > 5% and R u1 > 3%.
For example, through the optimization and improvement strategy that the moving blade avoids the low-frequency exciting force frequency resonance, the moving blade of the 1200MW nuclear turbine avoids the low-frequency exciting force frequency resonance to perform operation optimization control:
(1) If R is d1 =3.60% > 5% and R u1 The design and monitoring of the model 1200MW nuclear turbine moving blade avoiding the low-frequency exciting force frequency resonance are qualified by being more than 3 percent in the range of 1.90%, and the design and monitoring of the model 1200MW nuclear turbine moving blade avoiding the low-frequency exciting force frequency resonance are proved to be in a controlled state, and the design and monitoring of the moving blade avoiding the low-frequency exciting force frequency resonance are finished.
S1408, the moving blade avoids the operation optimization control of the high-frequency exciting force frequency resonance.
The method is characterized in that by means of a dynamic strength and vibration design monitoring method for the nuclear turbine moving blades subjected to centrifugal force, low-frequency exciting force and high-frequency exciting force, operation optimization control is carried out on the nuclear turbine moving blades by avoiding frequency resonance of the high-frequency exciting force:
(1) If Δf h And the design and monitoring of the nuclear turbine moving blade avoiding the high-frequency exciting force frequency resonance are qualified, and the design and monitoring of the moving blade avoiding the high-frequency exciting force frequency resonance is finished.
(2) If Δf h Less than 5%, the nuclear turbine rotor blade avoids disqualification of high-frequency exciting force frequency resonance design monitoring, which indicates that the blade profile width and thickness, the structure round angle, the connecting structure, the shroud thickness and the material mark of the rotor blade need to be run, optimally controlled and improved in the design stage, and S1401 to S1408 are re-executed until deltaf h And more than or equal to 5 percent.
For example, through an optimized and improved strategy that the moving blades avoid the frequency resonance of the high-frequency exciting force, the moving blades of the 1200MW nuclear turbine are subjected to operation optimization control that the moving blades avoid the frequency resonance of the high-frequency exciting force:
(1) If Δf h The design monitoring of the model 1200MW nuclear turbine moving blade avoiding the frequency resonance of the high-frequency exciting force is qualified, and the design monitoring that the moving blade avoiding the frequency resonance of the high-frequency exciting force is in a controlled state is shown, and the design monitoring of the moving blade avoiding the frequency resonance of the high-frequency exciting force is finished.
S1409, the whole circle of connecting long blades avoids the operation optimization control of the frequency resonance of the high-frequency exciting force.
The method for monitoring the dynamic strength and vibration of the nuclear turbine rotor blade subjected to the effects of centrifugal force, low-frequency exciting force and high-frequency exciting force is used for carrying out operation optimization control on the whole circle of connection long blades of the nuclear turbine by avoiding high-frequency exciting force frequency resonance:
(1) If Δf m And the design monitoring of the whole circle of connection long blades of the nuclear turbine avoiding the frequency resonance of the high-frequency exciting force is qualified, and the design monitoring of the whole circle of connection long blades avoiding the frequency resonance of the high-frequency exciting force is finished.
(2) If Δf m Less than 5%, emptyThe nuclear turbine is connected with long blades in whole circle to avoid disqualification of frequency resonance design monitoring of high-frequency exciting force, which indicates that the blade profile width and thickness, structural fillets, connecting structure, shroud thickness, material mark and the like of the final-stage moving blade need to be improved in operation optimization control in the design stage, and S1401 to S1409 are re-executed until deltaf m And more than or equal to 5 percent.
For example, through the optimization and improvement strategy that the whole circle of connecting long blades avoid the frequency resonance of the high-frequency exciting force, the operation optimization control is performed on the whole circle of connecting long blades of the 1200MW nuclear turbine to avoid the frequency resonance of the high-frequency exciting force:
(1) If Δf m The design monitoring that the whole circle of connection long blades of the 1200MW nuclear turbine avoid the frequency resonance of the high-frequency exciting force is qualified, and the design monitoring that the whole circle of connection long blades avoid the frequency resonance of the high-frequency exciting force is in a controlled state is shown, and the design monitoring that the whole circle of connection long blades avoid the frequency resonance of the high-frequency exciting force is finished.
According to the embodiment of the disclosure, the dynamic intensity and the safety of vibration of the moving blades of the nuclear turbine can be accurately monitored, and the operation of the nuclear turbine is optimally controlled, so that the service life of the nuclear turbine is prolonged, and the long-period safe operation of the nuclear turbine is ensured.
In a practical application scenario, the reliability design monitoring can be performed on torsional vibration safety of a multi-rotor system of a nuclear turbine bearing an electric disturbance fault of a power grid, and can be understood with reference to fig. 15, and fig. 15 is a schematic flow diagram of a method for monitoring reliability of a nuclear turbine by a combined monitoring platform of the nuclear turbine according to another embodiment of the disclosure, as shown in fig. 15, the method includes:
S1501, calculating the torsional vibration setting quantity of the multi-rotor system bearing the electric disturbance fault of the power grid.
Based on a component model database, a load database and a material database of the nuclear turbine, inputting design parameters, a three-dimensional mechanical model and material mechanical property data of a multi-rotor system of the nuclear turbine, and calculating the most significant value of the multi-rotor system of the nuclear turbine by using a torsional vibration design monitoring method and a subprogram of the multi-rotor system for bearing electric disturbance faults of a power gridTorsional vibration frequency F near 45Hz 1 Torsional vibration frequency F closest to the torsional vibration frequency of 55Hz 2 Torsional vibration frequency F closest to 93Hz 3 Torsional vibration frequency F closest to 108Hz 4 Maximum shear stress sigma of multi-rotor system of nuclear turbine during two-phase short circuit τmax 。
For example, based on a component model database, a load database and a material database of a nuclear turbine, design parameters, a three-dimensional mechanical model and material mechanical property data of a multi-rotor system of the 1200MW nuclear turbine are input, and a torsional vibration design monitoring method and a subroutine for bearing electric disturbance faults of a power grid of the multi-rotor system are used for calculating a torsional vibration frequency F closest to 45Hz of the multi-rotor system of the 1200MW nuclear turbine 1 Torsional vibration frequency F of =15.58 Hz, closest to 55Hz 2 Torsional vibration frequency F of =15.58 Hz, closest to 93Hz 3 = 90.51Hz, the torsional vibration frequency F closest to 108Hz 4 Maximum shear stress sigma of multi-rotor system of nuclear turbine during 172.14Hz and two-phase short circuit τmax ＝275.83Mpa。
S1502, calculating the ratio of the torsional vibration frequency of the multi-rotor system to the working frequency of the power grid.
Lower limit ratio R of torsional vibration frequency of multi-rotor system of nuclear turbine avoiding power grid working frequency L1 And upper limit ratio R H1 The calculation is respectively carried out according to the following formula:
in the above formula, F 1 At a torsional vibration frequency of closest 45Hz, F 2 Is the torsional vibration frequency closest to the torsional vibration frequency of 55 Hz.
For example, the torsional vibration frequency of the multi-rotor system of the 1200MW nuclear turbine avoids the working frequency of the power gridLower limit ratio R L1 And upper limit ratio R H1 The calculation is respectively carried out according to the following formula:
in the above formula, F 1 Is closest to 45Hz and has a torsional vibration frequency of 15.58Hz and F 2 The torsional vibration frequency is 87.61Hz which is the torsional vibration frequency closest to 55 Hz.
S1503, calculating the ratio of the torsional vibration frequency of the multi-rotor system to the double working frequency of the power grid.
Lower limit ratio R of torsional vibration frequency of multi-rotor system of nuclear turbine avoiding double working frequency of power grid L2 And upper limit ratio R H2 The calculation is respectively carried out according to the following formula:
in the above formula, F 3 At a torsional vibration frequency of closest 93Hz, F 4 Is the torsional vibration frequency closest to 108 Hz.
For example, the torsional vibration frequency of the multi-rotor system of the 1200MW nuclear turbine avoids the lower limit ratio R of the double working frequency of the power grid L2 And upper limit ratio R H2 The calculation is respectively carried out according to the following formula:
in the above formula, F 3 90.51Hz and F are the torsional vibration frequencies closest to 93Hz 4 Is 172.14Hz which is the torsional vibration frequency closest to 108 Hz.
S1504, calculating the torsional stress ratio of the multi-rotor system when two phases are short-circuited.
Torsional vibration stress ratio R of multi-rotor system of nuclear turbine when two-phase short circuit occurs in electric power system στ The calculation is carried out according to the following formula:
in the above formula, sigma τmax Is the maximum shear stress of the multi-rotor system when the two phases of the power grid are short-circuited,
is the yield limit of the material at the operating temperature.
For example, torsional vibration stress ratio R of multi-rotor system of nuclear turbine when two-phase short circuit occurs in electric power system στ The calculation is carried out according to the following formula:
above, sigma τmax The maximum shearing stress of the multi-rotor system is 275.83MPa when the two phases of the power grid are short-circuited,
is the yield limit of 630Mpa for the material at the operating temperature.
S1505, the torsional vibration frequency of the multi-rotor system avoids the operation optimization control of the working frequency of the power grid.
By means of a torsional vibration design monitoring method for bearing electric disturbance faults of a power grid of a multi-rotor system of a nuclear turbine, the torsional vibration frequency of the multi-rotor system of the nuclear turbine avoids the working frequency of the power grid and performs operation optimization control:
(1) If R is L1 < 1 and R H1 The design monitoring of the multi-rotor system torsional vibration frequency avoiding power grid working frequency of the nuclear turbine is qualified, and the design monitoring of the multi-rotor system torsional vibration frequency avoiding power grid working frequency is finished.
(2) If R is L1 Not less than 1 or R H1 The torsional vibration frequency of the multi-rotor system of the nuclear turbine is not more than 1, and design monitoring of avoiding the working frequency of a power grid is unqualified, which shows that the structure of a rotor or a coupling needs to be improved in operation optimization control in the design stage, materials with better yield strength are used, or the structural geometric dimension of the multi-rotor system is optimized, and S1501 to S1505 are re-executed until R is reached L1 < 1 and R H1 > 1.
For example, by a torsional vibration design monitoring method for bearing electric disturbance faults of a power grid of a multi-rotor system of a nuclear turbine, the torsional vibration frequency of the multi-rotor system of the 1200MW nuclear turbine avoids the working frequency of the power grid and performs operation optimization control:
(1) If R is L1 =0.35 < 1 and R H1 The design monitoring of the multi-rotor system torsional vibration frequency avoiding power grid working frequency of the 1200MW nuclear turbine is qualified, and the design monitoring of the multi-rotor system torsional vibration frequency avoiding power grid working frequency is proved to be in a controlled state, and the design monitoring of the multi-rotor system torsional vibration frequency avoiding power grid working frequency is finished.
S1506, the torsional vibration frequency of the multi-rotor system avoids the operation optimization control of the double working frequency of the power grid.
By means of a torsional vibration design monitoring method for bearing electric disturbance faults of a power grid of a multi-rotor system of a nuclear turbine, operation optimization control is carried out on torsional vibration frequencies of the multi-rotor system of the nuclear turbine while avoiding double working frequencies of the power grid:
(1) If R is L2 < 1 and R H2 The design monitoring that the torsional vibration frequency of the multi-rotor system of the nuclear turbine avoids the double working frequency of the power grid is qualified, and the design monitoring shows that the torsional vibration frequency of the multi-rotor system avoids the double working frequency of the power grid to be in a controlled state, and the torsional vibration frequency of the multi-rotor system avoids the double working frequency of the power gridAnd (5) finishing the design monitoring of the double working frequency of the power grid.
(2) If R is L2 Not less than 1 or R H2 The torsional vibration frequency of the multi-rotor system of the nuclear turbine is not more than 1, the design monitoring of avoiding the double working frequency of the power grid is unqualified, which shows that the structure of a rotor or a coupling needs to be improved in operation optimization control in the design stage, materials with better yield strength are used, or the geometric dimension of the structure of the multi-rotor system is optimized, and S1501 to S1506 are re-executed until R is reached L2 < 1 and R H2 > 1.
For example, by a torsional vibration design monitoring method for bearing electric disturbance faults of a power grid of a multi-rotor system of a nuclear turbine, the torsional vibration frequency of the multi-rotor system of the 1200MW nuclear turbine avoids double working frequency of the power grid and performs operation optimization control:
(1) If R is L2 =0.97 < 1 and R H2 The design monitoring of the model 1200MW nuclear turbine multi-rotor system torsional vibration frequency avoiding the double working frequency of the power grid is qualified, and the design monitoring of the multi-rotor system torsional vibration frequency avoiding the double working frequency of the power grid is in a controlled state, and the design monitoring of the multi-rotor system torsional vibration frequency avoiding the double working frequency of the power grid is finished.
S1507, the operation optimization control of torsional stress of the multi-rotor system when two-phase short circuit occurs.
By means of a torsional vibration design monitoring method for bearing electric disturbance faults of a multi-rotor system of a nuclear turbine, torsional vibration stress of the multi-rotor system of the nuclear turbine when two-phase short circuits occur is optimally controlled:
(1) If R is στ And (2) when the two-phase short circuit occurs, the torsional vibration stress design monitoring of the multi-rotor system of the nuclear turbine is qualified, which shows that the torsional vibration stress of the multi-rotor system is in a controlled state, and the torsional vibration stress design monitoring of the multi-rotor system is finished.
(2) If R is στ Not less than 1, and unqualified torsional vibration stress design monitoring of the multi-rotor system of the nuclear turbine when two-phase short circuit occurs, which indicates that the structure of the rotor or the coupling needs to be optimized, controlled and improved in the design stage, and materials with better yield strength are used instead, or the multi-rotor is optimizedThe structural geometry of the system is re-executed S1501 to S1507 until R στ And < 1.
For example, by a torsional vibration design monitoring method for bearing electric disturbance faults of a power grid by a multi-rotor system of a nuclear turbine, the torsional vibration stress of the 1200MW nuclear turbine multi-rotor system with the model number when two-phase short circuit occurs is optimally controlled:
(1) If R is στ When two-phase short circuit occurs, the torsional stress design monitoring of the model 1200MW nuclear turbine multi-rotor system is qualified, which indicates that the torsional stress of the multi-rotor system is in a controlled state, and the torsional stress design monitoring of the multi-rotor system is finished.
In the embodiment of the disclosure, the torsional vibration safety design condition of the multi-rotor system of the nuclear turbine bearing the electric disturbance fault of the power grid can be accurately monitored, so that the operation optimization control of the nuclear turbine is facilitated, the service life of the nuclear turbine is prolonged, and the long-period safe operation of the nuclear turbine is ensured.
In a practical application scenario, reliability design monitoring can be performed on shafting vibration safe operation of a rotor and a bearing system of a nuclear turbine under the actions of forced vibration and self-excited vibration, and as can be understood with reference to fig. 16, fig. 16 is a schematic flow diagram of a method for monitoring reliability of the nuclear turbine by a combined monitoring platform of the nuclear turbine according to another embodiment of the disclosure, as shown in fig. 16, the method includes:
s1601, inputting a shafting vibration online monitoring value of the forced vibration and self-excited vibration of the rotor and bearing system.
Based on a component model database, a load database and a material database of the nuclear turbine, a shafting vibration operation monitoring method and a subprogram for the rotor and bearing system bearing the forced vibration and self-excited vibration, and a relative displacement peak value D of the shaft vibration is input into the online monitoring of the rotor shaft journal of the nuclear turbine p-pr Vibration speed V (μm) on-line monitoring of bearing seat b (mm/s), and running vibration safety monitoring is performed.
For example, based on a component model database, a load database and a materials database of the nuclear turbine,shaft system vibration operation monitoring method and subprogram for bearing forced vibration and self-excitation vibration of rotor and bearing system, input into the 1200MW nuclear turbine rotor journal on-line monitoring shaft vibration relative displacement peak value D p-pr On-line monitoring vibration speed V of =100 μm and bearing seat b Run vibration safety monitoring was performed =4 mm/s.
S1602, calculating the ratio of the relative displacement of the on-line monitoring shaft vibration of the rotor shaft journal.
On-line monitoring shaft vibration relative displacement ratio R of nuclear turbine rotor shaft neck p-pr The calculation is carried out according to the following formula:
in the above formula, D p-pr The peak-to-peak value (mu m) of the relative displacement of the shaft vibration is monitored on line for the rotor shaft neck of the nuclear turbine.
For example, the rotor shaft neck of the 1200MW nuclear turbine online monitor shaft vibration relative displacement ratio R p-pr The calculation is carried out according to the following formula:
in the above formula, D p-pr The relative displacement peak and peak value of the shaft vibration are monitored on line for the rotor journal of the 1200MW nuclear turbine.
S1603, calculating the ratio of the on-line monitoring vibration speed of the bearing seat.
On-line monitoring vibration speed V of bearing seat of nuclear turbine b Ratio R b The calculation is carried out according to the following formula:
in the above formula, V b Vibration speed (mm/s) [ V ] for bearing housing on-line monitoring b ]The bearing seat is monitored on line for an alarm value (mm/s) of the vibration speed.
For example, the type 1200MW nuclear turbine bearing pedestal monitors vibration velocity V on line b Ratio R b The calculation is carried out according to the following formula:
in the above formula, V b For on-line monitoring of vibration speed of bearing seat, V b ＝4mm/s，[V b ]On-line monitoring of vibration speed alarm value (mm/s) for bearing seat, for n 0 Half-rotation speed nuclear turbine [ V ] with speed of 1500r/min and 1800r/min b ]=5.3 mm/s for n 0 Full-rotation-speed nuclear turbine [ V ] with values of 3000r/min and 3600r/min b ]＝7.5mm/s。
S1604, the rotor shaft neck monitors the running optimization control of the relative displacement of the shaft vibration on line.
The method for monitoring the shafting vibration operation of the nuclear turbine rotor and the bearing system under the actions of forced vibration and self-excited vibration is used for carrying out operation and maintenance optimization control on the on-line monitoring of the relative displacement of the shaft vibration of the nuclear turbine rotor shaft neck:
(1) If R is p-pr And (2) the operation monitoring of the on-line monitoring shaft vibration relative displacement of the rotor shaft journal of the nuclear turbine is qualified, and the on-line monitoring shaft vibration relative displacement of the rotor shaft journal of the nuclear turbine is in a controlled state.
(2) If R is p-pr Not less than 1, the on-line monitoring of the displacement operation of the relative shaft vibration of the rotor shaft neck of the nuclear turbine is unqualified, which indicates that the rotor and the bearing of the turbine are required to be overhauled in the using stage, the reason for the overlarge vibration of the rotor and the bearing is searched and improved, and S1601 to S1604 are re-executed until R p-pr And < 1.
For example, the operation and maintenance optimization control is performed on the shaft vibration relative displacement of the 1200MW nuclear turbine rotor journal through the shaft vibration operation monitoring method that the nuclear turbine rotor and the bearing system bear the forced vibration and self-excited vibration.
Due to R p-pr =0.833 < 1, the 1200MW nuclear turbine rotor shaftAnd the displacement operation monitoring of the on-line monitoring shaft vibration relative of the neck is qualified, so that the on-line monitoring shaft vibration relative displacement of the rotor shaft neck of the nuclear turbine is in a controlled state.
S1605, the bearing pedestal monitors the optimal control of the vibration speed on line.
The method for monitoring the shafting vibration operation of the nuclear turbine rotor and bearing system under the actions of forced vibration and self-excited vibration is used for carrying out operation and maintenance optimization control on the on-line monitoring vibration speed of the bearing seat of the nuclear turbine:
(1) If R is p-pb And (2) the operation monitoring of the on-line monitoring vibration speed of the bearing pedestal of the nuclear turbine is qualified, which shows that the on-line monitoring tile vibration displacement of the bearing of the nuclear turbine is in a controlled state.
(2) If R is b Not less than 1, the operation monitoring of the on-line monitoring vibration speed of the bearing seat of the nuclear turbine is unqualified, which indicates that the rotor and the bearing of the turbine are required to be overhauled in the using stage, the reason for overlarge vibration of the rotor and the bearing is searched for and improved, and S1601 to S1605 are re-executed until R b And < 1.
For example, the on-line monitoring vibration speed of the bearing pedestal of the 1200MW nuclear turbine is controlled in an operation and maintenance optimization mode by a shafting vibration operation monitoring method that the rotor and the bearing system of the nuclear turbine bear the actions of forced vibration and self-excited vibration.
(1) In view of R b The model 1200MW nuclear turbine bearing pedestal online monitoring vibration speed operation monitoring is qualified, which is less than 1 in the range of 0.755, and indicates that the nuclear turbine bearing pedestal online monitoring vibration speed is in a controlled state.
(2) If R is b Not less than 1, the operation monitoring of the on-line monitoring vibration speed of the bearing seat of the nuclear turbine is unqualified, which indicates that the rotor and the bearing of the turbine are required to be overhauled in the using stage, the reason for overlarge vibration of the rotor and the bearing is searched for and improved, and S1601 to S1605 are re-executed until R b And < 1.
According to the embodiment of the disclosure, the safety of shafting vibration of the rotor and the bearing system of the nuclear turbine can be accurately monitored, the operation and maintenance optimization control is performed on the nuclear turbine, the service life and the operation reliability of the nuclear turbine are improved, and the long-period safe operation of the nuclear turbine is ensured.
In the description of the present specification, a description referring to terms "one embodiment," "some embodiments," "examples," "specific examples," or "some examples," etc., means that a particular feature, structure, material, or characteristic described in connection with the embodiment or example is included in at least one embodiment or example of the present disclosure. In this specification, schematic representations of the above terms are not necessarily directed to the same embodiment or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments or examples. Furthermore, the different embodiments or examples described in this specification and the features of the different embodiments or examples may be combined and combined by those skilled in the art without contradiction.
Furthermore, the terms "first," "second," and the like, are used for descriptive purposes only and are not to be construed as indicating or implying a relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defining "a first" or "a second" may explicitly or implicitly include at least one such feature. In the description of the present disclosure, the meaning of "a plurality" is at least two, such as two, three, etc., unless explicitly specified otherwise.
Any process or method descriptions in flow charts or otherwise described herein may be understood as representing modules, segments, or portions of code which include one or more executable instructions for implementing specific logical functions or steps of the process, and additional implementations are included within the scope of the preferred embodiment of the present disclosure in which functions may be executed out of order from that shown or discussed, including substantially concurrently or in reverse order, depending on the functionality involved, as would be understood by those reasonably skilled in the art of the embodiments of the present disclosure.
Logic and/or steps represented in the flowcharts or otherwise described herein, e.g., a ordered listing of executable instructions for implementing logical functions, can be embodied in any computer-readable medium for use by or in connection with an instruction execution system, apparatus, or device, such as a computer-based system, processor-containing system, or other system that can fetch the instructions from the instruction execution system, apparatus, or device and execute the instructions. For the purposes of this description, a "computer-readable medium" can be any means that can contain, store, communicate, propagate, or transport the program for use by or in connection with the instruction execution system, apparatus, or device. More specific examples (a non-exhaustive list) of the computer-readable medium would include the following: an electrical connection (electronic device) having one or more wires, a portable computer diskette (magnetic device), a Random Access Memory (RAM), a read-only memory (ROM), an erasable programmable read-only memory (EPROM or flash memory), an optical fiber device, and a portable compact disc read-only memory (CDROM). In addition, the computer readable medium may even be paper or other suitable medium on which the program is printed, as the program may be electronically captured, via, for instance, optical scanning of the paper or other medium, then compiled, interpreted or otherwise processed in a suitable manner, if necessary, and then stored in a computer memory.
It should be understood that portions of the present disclosure may be implemented in hardware, software, firmware, or a combination thereof. In the above-described embodiments, the various steps or methods may be implemented in software or firmware stored in a memory and executed by a suitable instruction execution system. As with the other embodiments, if implemented in hardware, may be implemented using any one or combination of the following techniques, as is well known in the art: discrete logic circuits having logic gates for implementing logic functions on data signals, application specific integrated circuits having suitable combinational logic gates, programmable Gate Arrays (PGAs), field Programmable Gate Arrays (FPGAs), and the like.
Those of ordinary skill in the art will appreciate that all or a portion of the steps carried out in the method of the above-described embodiments may be implemented by a program to instruct related hardware, where the program may be stored in a computer readable storage medium, and where the program, when executed, includes one or a combination of the steps of the method embodiments.
Furthermore, each functional unit in the embodiments of the present disclosure may be integrated in one processing module, or each unit may exist alone physically, or two or more units may be integrated in one module. The integrated modules may be implemented in hardware or in software functional modules. The integrated modules may also be stored in a computer readable storage medium if implemented in the form of software functional modules and sold or used as a stand-alone product.
The above-mentioned storage medium may be a read-only memory, a magnetic disk or an optical disk, or the like. Although embodiments of the present disclosure have been shown and described above, it will be understood that the above embodiments are illustrative and not to be construed as limiting the present disclosure, and that variations, modifications, alternatives, and variations may be made to the above embodiments by one of ordinary skill in the art within the scope of the present disclosure.
It should be appreciated that various forms of the flows shown above may be used to reorder, add, or delete steps. For example, the steps recited in the present disclosure may be performed in parallel, sequentially, or in a different order, provided that the desired results of the disclosed aspects are achieved, and are not limited herein.
Claims (14)
1. The utility model provides a joint monitoring platform of nuclear turbine, its characterized in that, monitoring platform is distributed network structure, includes:
the system comprises a data processing server, a load database, a material database and a scheduling server, wherein the data processing server is connected with the load database and the material database;
the load database is used for storing load data and running state data of the nuclear turbine under a plurality of working conditions;
The material database is used for storing material performance data of the nuclear turbine;
the data processing server is configured to obtain a monitoring instruction for the nuclear turbine, where the monitoring instruction is at least one of a life monitoring instruction, a safety monitoring instruction and a reliability monitoring instruction of the nuclear turbine, determine a target monitoring object and a target dimension of the nuclear turbine based on the monitoring instruction, call the load database and the material database according to the monitoring object and the target dimension, obtain operation state data and load data matched with the target monitoring object and the target dimension from the load database, determine monitoring data corresponding to the monitoring instruction according to the matched operation state data and load data and the material performance data, and generate an optimization and improvement policy of the nuclear turbine according to the monitoring data, where the optimization and improvement policy includes a value of an object to be optimized, a parameter to be optimized, and a parameter to be optimized of the nuclear turbine, where the monitoring data includes at least one of life monitoring data, safety monitoring data and reliability monitoring data; the target monitoring object comprises the service life, the operation safety and the operation reliability of the nuclear turbine; according to the component parts of the nuclear turbine, different target monitoring dimensions corresponding to the target monitoring objects are determined;
The scheduling server is used for receiving the monitoring instructions and scheduling the monitoring instructions so as to realize the simultaneous execution of a plurality of monitoring instructions;
the load database stores the following data:
the nuclear turbine comprises a pressure load, a centrifugal force load, a thermal load and a bolt pretightening force load;
the rigidity coefficient and the damping coefficient of the bearing oil film;
measuring the metal temperature at the depth of 85% -95% of the wall thickness of the inner cylinder;
the metal temperature of the measuring point is measured at the depth of 85% -95% of the wall thickness of the valve casing and the cylinder, and the metal temperature of the measuring point is measured at the depth of 45% -50% of the wall thickness of the valve casing and the cylinder;
the metal temperature outside the flange center facet under the condition of steam leakage at the weakest part of the flange center facet tightness of the cylinder;
the nuclear turbine rotor shaft neck online monitoring shaft vibration relative displacement peak-to-peak valueDOn-line monitoring vibration speed of p-pr and bearing seatV b ；
And a start-stop curve of the nuclear turbine.
2. The monitoring platform of claim 1, further comprising: a component model database; the component model database is connected with the data processing server;
the component model database is used for component design parameters and a three-dimensional mechanical model of the nuclear turbine;
The data processing server is further configured to call the component model database after the monitoring instruction is acquired, acquire the component design parameter and the three-dimensional mechanical model from the component model database, and determine monitoring data corresponding to the monitoring instruction based on the component design parameter, the three-dimensional mechanical model, running state data and load data matched with the monitoring instruction, and the material performance data.
3. The monitoring platform of claim 1, wherein at least one of the data is stored in the materials database:
the material physical property, the material mechanical property, the mechanical property at high temperature and long time and the fatigue fracture mechanical property of the nuclear turbine.
4. A monitoring platform according to any one of claims 2 to 3, wherein the data processing server performs an operation optimization control of the nuclear turbine according to the optimization improvement strategy.
5. The monitoring platform of claim 4, further comprising: the webpage server is connected with the data processing server;
the webpage server is used for receiving the data sent by the data processing server and rendering the webpage based on the data to generate webpage data.
6. The monitoring platform of claim 5, further comprising:
the client browser is connected with the webpage server;
the client browser is used for responding to a browsing instruction input by a user, sending the browsing instruction to the webpage server, and receiving the webpage data sent by the webpage server for display.
7. The monitoring platform of claim 5, wherein the web server is further configured to receive the monitoring data sent by the data processing server, and render a web page based on the monitoring data to generate first type of web page data.
8. The monitoring platform of claim 5, wherein the web server is further configured to receive the optimization improvement policy sent by the data processing server, and render a web page based on the optimization improvement policy to generate a second type of web page data.
9. The monitoring platform of claim 5, comprising a plurality of said data processing servers and a plurality of said web servers;
the scheduling server is used for receiving the monitoring instruction, scheduling the monitoring instruction, determining a target data processing server and a target webpage server corresponding to the monitoring instruction, and sending identification information of the monitoring instruction and the target webpage server to the target data processing server;
The target data processing server is used for receiving the monitoring instruction, processing the monitoring instruction, generating corresponding data, and sending the corresponding data corresponding to the monitoring instruction to the target webpage server based on the identification information.
10. The monitoring platform of claim 9, wherein the scheduling server is further configured to:
acquiring a first load state of each data processing server and a second load state of each web server;
and scheduling the monitoring instruction according to the first load state and the second load state, and determining the target data processing server and the target web server.
11. The monitoring platform of claim 1, wherein the data processing server is further configured to:
acquiring running state data matched with the target monitoring object and the target monitoring dimension from the load database according to the target monitoring object and the target monitoring dimension;
and determining the monitoring data corresponding to the monitoring instruction according to the matched running state data, the material performance data, the component design parameters and the three-dimensional mechanical model.
12. The monitoring platform of claim 1, wherein the data processing server is further configured to:
when the monitoring instruction is the service life monitoring instruction, acquiring running state data and load data matched with the service life monitoring instruction and the material performance data;
based on the operational status data and load data matched to the life monitoring instructions, and the material performance data, at least one of the following data is obtained:
acquiring first life monitoring data of low cycle fatigue and high cycle fatigue of a rotor of the nuclear turbine under a plurality of working conditions under the actions of centrifugal force, thermal load and gravity load;
acquiring second life monitoring data of low cycle fatigue and creep under the pressure and thermal load action of a valve casing and a cylinder of the nuclear turbine under multiple working conditions;
acquiring third service life monitoring data of the rotor, the valve housing and the cylinder of the nuclear turbine under the multi-working condition of bearing the rapid starting thermal stress;
and determining the first life monitoring data, the second life monitoring data and the third life monitoring data as life monitoring data of the nuclear turbine.
13. The monitoring platform of claim 1, wherein the data processing server is further configured to:
When the monitoring instruction is the safety monitoring instruction, acquiring running state data and load data matched with the safety monitoring instruction and the material performance data;
based on the operational status data and load data matched with the safety monitoring instructions, and the material performance data, at least one of the following data is obtained:
acquiring first intensity safety monitoring data of the nuclear turbine subjected to scaling, abrasion, corrosion and water erosion damage, which lead to power reduction and stress corrosion;
acquiring second intensity security monitoring data of a steady state and a transient state of a rotor of the nuclear turbine under the action of centrifugal force and thermal load;
acquiring steady-state and transient third-intensity security monitoring data of a valve housing and a cylinder of the nuclear turbine under the action of pressure and thermal load;
acquiring safety design monitoring data and safety operation monitoring data of a split surface of a flange under the action of bearing load, thermal load and bolt pretightening force load of a cylinder of the nuclear turbine;
and determining the first intensity security monitoring data, the second intensity security monitoring data, the third intensity security monitoring data, the security design monitoring data and the security operation monitoring data as security monitoring data of the nuclear turbine.
14. The monitoring platform of claim 1, wherein the data processing server is further configured to:
when the monitoring instruction is the reliability monitoring instruction, acquiring running state data and load data matched with the reliability monitoring instruction and the material performance data;
based on the operational status data and load data matched with the reliability monitoring instructions, and the material property data, at least one of the following data is obtained:
acquiring dynamic strength and vibration reliability monitoring data of the action of centrifugal force, low-frequency exciting force and high-frequency exciting force borne by a moving blade of the nuclear turbine;
acquiring torsional vibration reliability monitoring data of a multi-rotor system of the nuclear turbine, wherein the torsional vibration reliability monitoring data bear electric disturbance faults of a power grid;
acquiring first shafting vibration reliability monitoring data of a rotor and bearing system of the nuclear turbine, wherein the first shafting vibration reliability monitoring data bear the actions of forced vibration and self-excited vibration;
acquiring second axis vibration reliability monitoring data of the rotor and bearing system of the nuclear turbine under the actions of forced vibration and self-excited vibration;
and determining the dynamic intensity and vibration monitoring data, torsional vibration monitoring data, the first shafting vibration reliability monitoring data and the second shafting vibration reliability monitoring data as the reliability monitoring data of the nuclear turbine.
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| CN202111456675.3A CN114398751B (en) | 2021-12-01 | 2021-12-01 | Combined monitoring platform of nuclear turbine |
| US17/691,040 US11725534B2 (en) | 2021-12-01 | 2022-03-09 | Method of multi-objective and multi-dimensional online joint monitoring for nuclear turbine |
| AU2022201697A AU2022201697B2 (en) | 2021-12-01 | 2022-03-11 | Method and system of multi-objective and multi-dimensional online joint monitoring for nuclear turbine |
| FR2204652A FR3129765A1 (en) | 2021-12-01 | 2022-05-17 | Method and system for multi-objective and multi-dimensional joint online monitoring for a nuclear turbine |
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| CN116773374B (en) * | 2023-06-15 | 2024-05-31 | 上海发电设备成套设计研究院有限责任公司 | Cylinder stress corrosion and low cycle fatigue long life monitoring method for nuclear turbine |
| CN116773667B (en) * | 2023-06-15 | 2024-05-24 | 上海发电设备成套设计研究院有限责任公司 | Method and device for monitoring crack safety of rotor blade root groove of nuclear turbine |
| CN116773666B (en) * | 2023-06-15 | 2024-04-26 | 上海发电设备成套设计研究院有限责任公司 | Method and device for monitoring stress corrosion and fatigue safety of nuclear turbine |
| CN116776587B (en) * | 2023-06-15 | 2024-07-05 | 上海发电设备成套设计研究院有限责任公司 | Nuclear turbine life-cycle stress corrosion and fatigue safety monitoring platform and method |
| CN117666408A (en) * | 2023-10-24 | 2024-03-08 | 上海发电设备成套设计研究院有限责任公司 | Multi-dimensional monitoring platform for flexibly operating steam turbine |
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