CN114398751A - Combined monitoring platform of nuclear turbine

Info

Abstract

Description

Claims

CN114398751A

Publication number: CN114398751A
Application number: CN202111456675.3A
Authority: CN
Inventors: 史进渊; 范雪飞; 张绪炎; 李俊昆; 郝宁; 徐望人
Original assignee: Shanghai Power Equipment Research Institute Co Ltd
Current assignee: Shanghai Power Equipment Research Institute Co Ltd
Priority date: 2021-12-01
Filing date: 2021-12-01
Publication date: 2022-04-26
Anticipated expiration: 2041-12-01
Also published as: CN114398751B

The utility model 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 operation state data of the nuclear turbine under multiple working conditions; the material database is used for storing material performance data of the nuclear turbine; the data processing server is used for obtaining 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 monitoring system realizes the monitoring of the nuclear turbine with long service life, high safety and high reliability, optimizes the monitoring effect of the nuclear turbine and reduces the monitoring difficulty.

Combined monitoring platform of nuclear turbine

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 various damage mechanism effects in the operation process, so that the related performance of the nuclear turbine is damaged to a certain degree, and further, the operation state and other related attribute parameters of the nuclear turbine are influenced to a certain degree.

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 is directed to solving, at least to some extent, one of the technical problems in the related art.

Therefore, the disclosure provides a combined monitoring platform of a nuclear turbine.

The utility model provides a combined monitoring platform of nuclear power steam turbine, includes: 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 operation state data of the nuclear turbine under multiple 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 for the nuclear turbine, 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, calling the load database and the material database, acquiring running state data and load data matched with the monitoring instruction from the load database, and determining monitoring data corresponding to the monitoring instruction according to the matched running state data and load data and the material performance data, wherein the monitoring data comprises at least one of service life monitoring data, safety monitoring data and reliability monitoring data.

The data server acquires running state data, load data and material performance data corresponding to the monitoring instructions from the load database and the material database connected with the data server based on the acquired monitoring instructions, and further acquires the monitoring data corresponding to the monitoring instructions. Further, monitoring of the nuclear turbine by the nuclear turbine combined monitoring platform is achieved based on monitoring data corresponding to the monitoring instructions. According to the monitoring method and the monitoring system, through the combined monitoring platform of the nuclear turbine, effective monitoring coverage of the nuclear turbine with long service life, high safety and high reliability 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 disclosure, nor is it intended to be used to limit the scope of the disclosure. Other features of the present disclosure will become apparent from the following description.

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 of which:

FIG. 1 is a schematic structural diagram of a combined monitoring platform of a nuclear turbine according to an embodiment of the present disclosure;

FIG. 2 is a schematic structural diagram of a combined monitoring platform of a nuclear turbine according to another embodiment of the present disclosure;

FIG. 3 is a schematic structural diagram of a combined monitoring platform for a nuclear turbine according to another embodiment of the present disclosure;

FIG. 4 is a schematic flow chart illustrating a monitoring method of a combined monitoring platform of a nuclear turbine according to an embodiment of the present disclosure;

FIG. 5 is a schematic flow chart illustrating a monitoring method for a combined monitoring platform of a nuclear turbine according to another embodiment of the present disclosure;

FIG. 6 is a schematic flow chart of a method for monitoring the service life of a nuclear turbine by a combined monitoring platform of a nuclear turbine according to an embodiment of the present disclosure;

FIG. 7 is a schematic flow chart of a method for monitoring the service life of a nuclear turbine by a combined monitoring platform of a nuclear turbine according to another embodiment of the present disclosure;

FIG. 8 is a schematic flow chart of a method for monitoring the service life of a nuclear turbine by a combined monitoring platform of a nuclear turbine according to another embodiment of the present disclosure;

FIG. 9 is a schematic flow chart diagram illustrating a monitoring method for a combined monitoring platform of a nuclear turbine according to another embodiment of the present disclosure;

FIG. 10 is a schematic flow chart illustrating a method for monitoring the safety of a nuclear turbine by a combined monitoring platform of a nuclear turbine according to an embodiment of the present disclosure;

FIG. 11 is a schematic flow chart illustrating a method for monitoring the safety of a nuclear turbine by a combined monitoring platform of a nuclear turbine according to another embodiment of the present disclosure;

FIG. 12 is a schematic flow chart illustrating a method for monitoring the safety of a nuclear turbine by a combined monitoring platform of a nuclear turbine according to another embodiment of the present disclosure;

FIG. 13 is a schematic flow chart diagram illustrating a monitoring method for a combined monitoring platform of a nuclear turbine according to another embodiment of the present disclosure;

FIG. 14 is a schematic flow chart of a method for monitoring the reliability of a nuclear turbine by a combined monitoring platform of a nuclear turbine according to an embodiment of the present disclosure;

FIG. 15 is a schematic flow chart illustrating a method for monitoring the reliability of a nuclear turbine by a combined monitoring platform of a nuclear turbine according to another embodiment of the present disclosure;

fig. 16 is a schematic flow chart of a method for monitoring the reliability of a nuclear turbine by using a combined monitoring platform of a nuclear turbine according to another embodiment of the present disclosure.

Detailed Description

Reference will now be made in detail to the embodiments of the present disclosure, examples of which are illustrated in the accompanying drawings, wherein like or similar reference numerals refer to the same or similar elements or elements having the same or similar functions throughout. The embodiments described below with reference to the drawings are exemplary and intended to be illustrative of the present disclosure, and should not 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 drawings.

Fig. 1 is a schematic structural diagram of a combined monitoring platform of a nuclear turbine according to an embodiment of the present disclosure, and as shown in fig. 1, the combined monitoring platform 100 of the 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 components, and the operation of the nuclear turbine is realized based on the respective operation and the cooperative cooperation of each component. In the operation process of the nuclear turbine, different damage mechanism actions borne by different parts are different, so that the nuclear turbine can bear various damage borne mechanism actions in the operation process.

For example, a rotor of a nuclear turbine may suffer from low cycle fatigue life damage and high cycle fatigue life damage under the action of centrifugal force, thermal load and gravity load. For another example, the valve casing and the cylinder of a nuclear turbine have the possibility of low cycle fatigue life damage and creep life damage under the action of pressure and thermal load. For another example, a rotor, a valve casing and a cylinder of a nuclear turbine have the possibility of life damage under the action of quick starting thermal stress.

For example, a nuclear turbine may suffer from power loss and stress corrosion damage under the conditions of scaling, wear, corrosion, erosion, and the like. For another example, a rotor of a nuclear turbine may have a risk of insufficient steady-state and transient strength margins under the action of centrifugal force and thermal load. For another example, a cylinder of a nuclear turbine may face a risk of steam leakage from a mid-split surface of a cylinder flange under the action of a stress load, a thermal load and a bolt pre-tightening force load. For another example, the valve casing and the cylinder of the nuclear turbine may have a risk of insufficient steady-state and transient strength margins under the action of centrifugal force and thermal load.

For example, a moving blade of a nuclear turbine may be damaged by high-cycle fatigue under the action of centrifugal force, low-frequency exciting force and high-frequency exciting force. For another example, when a multi-rotor system of a nuclear turbine has a power grid electrical disturbance fault, there is a possibility of torsional vibration damage. For another example, a rotor and a bearing system of a nuclear turbine have the possibility of vibration damage of a shaft system under the action of forced vibration and self-excited vibration.

In the embodiment of the disclosure, the service life, the safety and the reliability of the nuclear turbine under the action of various damage mechanisms can be monitored through a combined monitoring platform of the nuclear turbine.

As shown in fig. 1, a combined monitoring platform 100 of a nuclear turbine includes a load database 12, where the load database 12 is used for storing 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, nuclear turbines are comprised of multiple components, such as rotors, valve housings, cylinders, moving blades, multi-rotor systems, bearing systems, and the like. Under different working conditions, the corresponding load and the operating state of each component are different, and further, the load data and the operating state data of each component of the nuclear turbine under each working condition can be stored in the load database 12.

The working conditions of the nuclear turbine can include stable working conditions, high transient conditions and the like.

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 the 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 acquired load data and operating state data of each component of the nuclear turbine under the high transient state working condition can 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 present disclosure, the combined monitoring platform 100 of the nuclear turbine is used for monitoring material properties of different components in the nuclear turbine, for example, for monitoring a low cycle fatigue life, a high cycle fatigue life, a steady-state strength, a transient strength, a low-frequency excitation force, a high-frequency excitation force, and the like of a material.

Therefore, the material performance data of different parts of the nuclear turbine needs to be operated in a relevant manner, so as to obtain the 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 combined monitoring platform 100 for a nuclear power turbine further includes a data processing server 11, where the data processing server 11 is configured to obtain a monitoring instruction for the nuclear power 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 power turbine, call a load database and a material database, obtain operating 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 operating state data and load data, and the material performance data, 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 sent to the data processing server 11 of the nuclear turbine. Wherein the monitoring instruction may include at least one of a lifetime monitoring instruction, a security monitoring instruction, and a reliability monitoring instruction.

Optionally, based on the obtained service life monitoring instruction for the nuclear turbine, the service life monitoring for the nuclear turbine can be realized.

According to the obtained service life monitoring instruction, the data processing server 11 can obtain corresponding operating state data and load data from the load database 12, obtain corresponding material performance data from the material database 13, and further determine service life monitoring data corresponding to the service life monitoring instruction, so that long-service life monitoring of the nuclear power turbine is achieved.

Optionally, based on the acquired 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 can obtain corresponding operating state data and load data from the load database 12, obtain corresponding material performance data from the material database 13, and further determine safety monitoring data corresponding to the safety monitoring instruction, so that high-safety monitoring on the nuclear power turbine is achieved.

Optionally, based on the obtained reliability monitoring instruction for the nuclear turbine, high-reliability monitoring on the nuclear turbine can be achieved.

According to the obtained reliability monitoring instruction, the data processing server 11 can obtain corresponding operating state data and load data from the load database 12, obtain corresponding material performance data from the material database 13, and further determine reliability monitoring data corresponding to the reliability monitoring instruction, so as to realize high-reliability monitoring on the nuclear power turbine.

In the above embodiment, the combined monitoring platform of the nuclear turbine further includes other modules, and with reference to fig. 2, fig. 2 is a schematic structural diagram of the combined monitoring platform of the nuclear turbine according to another embodiment of the present disclosure.

As shown in fig. 2, the joint monitoring platform 200 for a nuclear turbine includes a data processing server 21, a load database 22, a material database 23, a component model database 24, a web server 25, and a client browser 26, wherein the data processing server 21 is connected to the load database 22 and the material database 23, the component model database 24 is connected to the data processing server 21, the web server 25 is connected to the data processing server 21, and the client browser 25 is connected to the web server 25.

In the embodiment of the present disclosure, the load database 22 is configured to store load data and operating state data of the nuclear turbine under multiple working conditions, where the load database 22 may store at least one of the following data:

pressure load, centrifugal force load, heat load and bolt pretightening force load of the nuclear turbine.

The rigidity coefficient and the damping coefficient of the bearing oil film.

The metal temperature of a measuring point at the depth of 85-95% of the wall thickness of the inner cylinder.

The metal temperature is measured at the position of 85% -95% of the wall thickness of the valve casing and the cylinder, and the metal temperature is measured at the position of 45% -50% of the wall thickness of the valve casing and the cylinder.

And the metal temperature outside the flange median plane is controlled under the condition that steam leaks from the weakest flange median plane of the cylinder.

Online monitoring of shaft vibration relative displacement peak value Dp-pr and online monitoring of vibration speed V of bearing seat for nuclear power steam turbine rotor shaft neck_b。

Start-stop curve of nuclear turbine.

The material database 23 is used for storing material performance data of the nuclear turbine, wherein at least one item of data can be stored in the material database 23: the material physical property, the material mechanical property, the high-temperature long-time mechanical property and the fatigue fracture mechanical property of the nuclear turbine.

It can be understood that the material database 23 stores performance parameter data of the constituent materials of each component constituting the nuclear turbine, where 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 may be used for generating 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 three-dimensional mechanical models of the nuclear turbine.

The data processing server 21 is further configured to, after the monitoring instruction is obtained, call the component model database 24, obtain 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 operating state data and the load data that are matched with the monitoring instruction, and the material performance data.

In implementation, the combined monitoring platform of the nuclear turbine may be controlled by a monitoring instruction, wherein the data processing server 21 may obtain the component design parameters and the three-dimensional mechanical model from the component model database 24 based on the monitoring instruction after obtaining the monitoring instruction.

Optionally, the component design parameters and the three-dimensional mechanical model can be used for monitoring the long service life and the high reliability of the nuclear turbine, and the component design parameters, the three-dimensional mechanical parameters and the running state data, the load data and the material performance data matched with the monitoring instructions are combined to obtain the long service life monitoring data and the high reliability monitoring data corresponding to the long service life monitoring instructions and the high reliability monitoring instructions.

In the embodiment of the present disclosure, the data processing server 21 may be further configured to generate an optimization and improvement strategy of the nuclear turbine according to the monitoring data, and perform operation optimization and control on the nuclear turbine according to the optimization and improvement strategy.

In order to realize effective monitoring of the nuclear turbine, after the monitoring data corresponding to the monitoring instruction is acquired, the data processing server 21 may generate an optimization and improvement strategy of the nuclear turbine according to the monitoring data. The optimization and improvement strategy can comprise values of an object to be optimized, a parameter to be optimized of the object to be optimized and the parameter to be optimized of the nuclear turbine after optimization.

It can be understood that the data processing server 21 can judge the service life, safety and reliability of the nuclear turbine according to the monitoring data, and can obtain an optimization improvement strategy corresponding to the nuclear turbine according to a judgment result.

And further, performing related optimization on the nuclear turbine according to an optimization 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 display.

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, wherein the web server 25 is configured to receive the data sent by the data processing server 21 and render the web page based on the data to generate web page data.

In the implementation, the visualization requirement exists for related data such as the monitoring condition of the nuclear turbine, so that the related data needing to be displayed can be sent to the webpage server 25, the webpage server 25 further renders the acquired related data, and then corresponding webpage data are generated.

Optionally, the web server 25 is further configured to receive monitoring data sent by the data processing server, and render the web page based on the monitoring data to generate first type 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 server 25 is further configured to receive the optimization and improvement policy sent by the data processing server, and render the web page based on the optimization and 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 that 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 second-class web data.

Further, the webpage data can be visually displayed through the client browser.

In the embodiment of the present disclosure, the joint monitoring platform 200 of a nuclear turbine further includes a client browser 26.

The client browser 26 is connected to the web server 25, wherein 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 and display web data sent by the web server 25.

In an implementation, a 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 call the web data corresponding to the data that the user needs to browse according to the attribute information carried in the browsing instruction, 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 webpage 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 webpage server, and the client browser is connected with the webpage server. Through the connection relation between different functional modules, realize the data interaction between the different functional modules, and then realized covering the effective control of long-life, high security and high reliability of nuclear power steam turbine, optimized the monitoring effect to nuclear power steam turbine, reduced the control degree of difficulty to nuclear power steam turbine.

In order to realize effective monitoring of the long service life, high safety and high reliability of the nuclear turbine, the joint monitoring platform of the nuclear turbine provided by the disclosure is in a distributed network structure, and fig. 3 can be combined, and fig. 3 is a schematic structural diagram of a joint 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 the monitoring instruction and the identification information of 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 a distributed network structure, so as to realize effective monitoring of the nuclear turbine in the same time period.

Furthermore, the multi-dimensional monitoring of the nuclear turbine can be realized 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 dimensions 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 available state of each data processing server and the web server.

The available state of the data processing server may be determined as a first load state, and the available state of the web server may be determined as a second load state.

Further, a first load status of each data processing server and a second load status of each web server are obtained. And scheduling the monitoring instruction according to the first load state and the second load state, and determining a target data processing server and a target webpage 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 can 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.

Correspondingly, 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 web data for the monitoring data corresponding to the monitoring instruction and the optimization improvement strategy can be judged according to the unoccupied space in the web server, so that the target web server corresponding to the monitoring instruction is determined.

In order to achieve 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 together.

And further, 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.

It is to be understood 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.

According to the combined monitoring platform of the nuclear turbine, the distributed network structure can be realized through the scheduling server, and the combined monitoring platform of the nuclear turbine comprises a plurality of data processing servers and a plurality of webpage servers. Furthermore, the scheduling server can determine an available target data processing server and an available target webpage server for the monitoring instruction according to the first load state of the data processing server and the second load state of the webpage server, so that the combined monitoring platform of the nuclear turbine can simultaneously execute a plurality of monitoring instructions. According to the monitoring method and the monitoring system, the monitoring coverage of the nuclear turbine combined monitoring platform on the nuclear turbine is optimized, the monitoring efficiency of the nuclear turbine combined monitoring platform is improved, and the monitoring effect of the nuclear turbine combined monitoring platform is optimized.

In the foregoing embodiment, regarding the determination of the target monitoring object and the target monitoring dimension by the data processing server, which can be further understood with reference to fig. 4, fig. 4 is a schematic flow chart of a monitoring method of a combined monitoring platform of a nuclear turbine according to an embodiment of the present disclosure, and as shown in fig. 4, 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 combined 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 may include the operation life, the operation safety, the operation reliability and the like of the nuclear turbine.

Furthermore, different target monitoring objects have different monitoring requirements, and the combined monitoring platform of the nuclear power turbine provided by the disclosure 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 components of the nuclear turbine.

For example, a target monitoring object is set as a life for a rotor of a nuclear turbine. When the rotor is subjected to centrifugal force, thermal load and gravity load, the low cycle fatigue life and the high cycle fatigue life of the rotor may be damaged, and therefore, the low cycle fatigue life and the high cycle fatigue life may be used as target monitoring dimensions for monitoring the life of the rotor based on a target monitoring object.

For another example, a target monitoring object is set as safety for a valve casing and a cylinder of a nuclear turbine. When the valve shell and the cylinder bear the pressure and the heat load, the steady-state strength and the transient strength of the valve shell and the cylinder have the possibility of changing, so that the steady-state strength and the transient strength can be used as target monitoring dimensions when the valve shell and the cylinder are used for safety monitoring based on a target monitoring object.

For another example, a target monitoring object is set as reliability for a moving blade of a nuclear turbine. When the moving blade is subjected to the action of centrifugal force, low-frequency excitation force and high-frequency excitation force, the dynamic strength and the vibration safety of the moving blade are possibly changed, so that the dynamic strength and the vibration safety can be used as target monitoring dimensions when the moving blade is monitored for reliability based on a target monitoring object.

S402, 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.

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 target monitoring object and the operation state data matched with 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 the tightness of the flange midplanes under the action of the bearing load, the thermal load and the bolt pre-tightening force load of the cylinder, so that the operation state data on the tightness dimension of the flange midplanes of the cylinder can be obtained from the load database, the tightness data of the flange midplanes of the cylinder can be included when the cylinder bears the corresponding force load, the tightness data of the flange midplanes of the cylinder can be included when the cylinder bears the corresponding thermal load, and the tightness data of the flange midplanes of the cylinder can be included when the cylinder bears the corresponding bolt pre-tightening force load.

For another example, if the target monitoring object is the service life of the nuclear turbine, and the target monitoring dimension is the service life of the rotor, the valve casing and the cylinder under the action of the rapid starting thermal stress, the service life data of the rotor, the valve casing and the cylinder under the action of the rapid starting thermal stress can be obtained from the load database.

For another example, if the target monitoring object is the reliability of the nuclear turbine, and the target monitoring dimension is the safe operation of the shafting vibration of the rotor and bearing system under the action of forced vibration and self-excited vibration, the shafting vibration monitoring data of the rotor and bearing system under the action of forced vibration and self-excited vibration can be obtained from the load database.

And S403, determining 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.

In the embodiment of the disclosure, the monitoring data of the target monitoring object in the target monitoring dimension can be acquired according to the operating state data, the material performance data, the component design parameters and the three-dimensional mechanical model.

The data processing server can acquire the running state data, the material performance data, the component design parameters and the 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 of the target monitoring object in the target monitoring dimension from the load database, acquire material performance data of the target monitoring object in the target monitoring dimension from the material database, and acquire part design parameters and a corresponding three-dimensional mechanical model of the target monitoring object in the target monitoring dimension from the part model database.

Further, based on the relevant 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, and then obtains running state data, material performance data, part design parameters and a three-dimensional mechanical model which are matched with the target monitoring object and the target monitoring dimension, and further obtains monitoring data corresponding to the monitoring instruction. According to the monitoring method and device, the monitoring data corresponding to the monitoring instruction is obtained based on integration of related data in different databases, accuracy of the monitoring data is guaranteed, and then optimization of the monitoring effect of the nuclear turbine is achieved.

The combined monitoring platform of a nuclear power turbine provided by the present disclosure can realize the monitoring of the service life of the nuclear power turbine, and can be further understood by referring to fig. 5, where fig. 5 is a schematic flow diagram of a monitoring method of a combined monitoring platform of a nuclear power turbine according to another embodiment of the present disclosure, and as shown in fig. 5, the method includes:

s501, when the monitoring instruction is a service life monitoring instruction, acquiring running state data and load data matched with the service 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.

Furthermore, the service life monitoring instruction can be received through a data processing server in the 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 operation state, the load borne by the nuclear turbine 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 operation 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 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 life monitoring instruction 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 under the action of centrifugal force, thermal load and gravity load borne by a rotor of a nuclear turbine under multiple working conditions;

acquiring second life monitoring data of low cycle fatigue and creep deformation under the action of pressure and thermal load borne by a valve shell and a cylinder of the nuclear turbine under multiple working conditions;

acquiring third life monitoring data of the rotor, the valve casing and the cylinder of the nuclear turbine under the action of rapid starting thermal stress under multiple working conditions;

and determining the first life monitoring data, the second life monitoring data and the third life monitoring data as the 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 operation process of a rotor of a nuclear turbine, the low cycle fatigue life and the high cycle fatigue life of the rotor may be damaged. For example, the valve casing of the nuclear turbine, during the operation process of the nuclear turbine, the creep life and the low-cycle fatigue life of the valve casing are possibly damaged.

Further, the data processing server may obtain at least one of the operation state data, the load data, and the material performance data matched with the life monitoring instruction as corresponding life monitoring data based on the life monitoring instruction.

Optionally, the data processing server may obtain first life monitoring data of low cycle fatigue and high cycle fatigue, which are subjected to centrifugal force, thermal load and gravity load, of the rotor of the nuclear turbine under multiple working conditions.

In the embodiment of the disclosure, during the operation 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 low cycle fatigue life and the high cycle fatigue life of the rotor are possibly damaged.

The rotor bears different centrifugal force, thermal load and gravity load under different working conditions, so that the low cycle fatigue life and the high cycle fatigue life of the rotor under different working conditions are possibly different.

Further, in order to realize the service 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 under the action of centrifugal force, thermal load and gravity load under a plurality of working conditions as corresponding service life monitoring data, and determine the data as the first service life monitoring data.

For example, the low cycle fatigue life data and the high cycle fatigue life data of the rotor under the action of the centrifugal force, the thermal load and the gravity load under the stable working condition can be used as first life monitoring data, and the low cycle fatigue life data and the high cycle fatigue life data of the rotor under the action of the centrifugal force, the thermal load and the gravity load under the high transient working condition can be used as first life monitoring data.

Optionally, second life monitoring data of low cycle fatigue and creep under the action of pressure and heat load under multiple working conditions of a valve casing and a cylinder of the nuclear turbine are obtained.

In the embodiment of the disclosure, the valve casing and the cylinder of the nuclear turbine can bear the pressure and the heat load during the operation of the nuclear turbine, so that the low-cycle fatigue life and the creep life of the valve casing and the cylinder of the nuclear turbine are possibly damaged.

Wherein, nuclear power steam turbine's valve casing and cylinder are under the operating mode of difference, and the pressure that its bore exists differently with the effect of heat load, and then make valve casing and cylinder low cycle fatigue life and creep life-span under different operating modes probably have the difference.

Further, in order to realize the service life monitoring of the valve casing and the cylinder of the nuclear turbine, the data processing server can 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 heat load under a plurality of working conditions as corresponding service life monitoring data, and determine the service life data as second service life monitoring data.

For example, can regard valve casing and cylinder as second life monitoring data with the low cycle fatigue life data and the creep life data that pressure and thermal load acted on under stable operating mode, can also regard valve casing and cylinder as second life monitoring data with the low cycle fatigue life data and the creep life data that pressure and thermal load acted on under high transient state operating mode.

Optionally, third life monitoring data of the rotor, the valve casing and the cylinder of the nuclear turbine under the action of rapid starting thermal stress under multiple working conditions are obtained.

In the implementation, the nuclear turbine has the requirement of quick starting. When the nuclear turbine needs to be started quickly, parts of assemblies such as a rotor, a valve casing and a cylinder in the nuclear turbine can bear the action of thermal stress caused by quick starting, and when the thermal stress acts on the parts of assemblies such as the rotor, the valve casing and the cylinder of the nuclear turbine, the service life of the parts of assemblies can be damaged.

The data processing server can obtain the service life data of the rotor, the valve shell and the cylinder under the action of the quick-start thermal stress, and the service life data is used as third service life monitoring data.

For example, can bear the life data of quick start thermal stress effect under stable operating mode with rotor, valve casing and cylinder as third life monitoring data, can also bear the life data of quick start thermal stress effect under high transient state operating mode with valve casing and cylinder as third life monitoring data.

And further, determining the first life monitoring data, the second life monitoring data and the third life monitoring data as the 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 when a rotor of the nuclear turbine bears centrifugal force, thermal load and gravity load, the second life monitoring data includes low cycle fatigue and creep life monitoring data when a valve casing and a cylinder of the nuclear turbine bear pressure and thermal load, and the third life monitoring data includes life monitoring data when the rotor, the valve casing and the cylinder of the nuclear turbine bear quick 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 achieved for parts needing 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 a combined monitoring platform of the nuclear turbine, and 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 obtained 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 obtained from a corresponding database, and then the service life monitoring data of the nuclear turbine matched with the service life monitoring instruction is determined. According to the monitoring method and device for the service life of the nuclear turbine, 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 embodiments, the implementation of the life monitoring of the nuclear turbine by the combined monitoring platform of the nuclear turbine and the determination of the optimization and improvement strategy of the nuclear turbine based on the result of the life monitoring may be further combined with the following embodiments.

In an actual application scenario, when a rotor of the nuclear power 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, it may be understood by referring to fig. 6 that the long-life design monitoring is performed when the low-cycle fatigue life and the high-cycle fatigue life of the rotor of the nuclear turbine, which bear centrifugal force, thermal load and gravity load, reach 60 years, and fig. 6 is a schematic flow chart of the method for monitoring the life of the nuclear turbine by using the combined monitoring platform of the nuclear turbine according to an embodiment of the present disclosure, as shown in fig. 6, the method includes:

s601, determining the starting and stopping times of the nuclear turbine.

Method and subprogram for designing and monitoring low-cycle fatigue and high-cycle fatigue life based on load database and inputting annual cold-state starting times y of nuclear turbine_cAnnual average temperature state starting times y_wAnnual average thermal state number of starts y_hNumber of normal annual stoppages y_nAnnual average 110% number of overspeed tests y₁₁₀Annual average operating hours t_yWorking speed n₀。

For example, for a certain type 1200MW nuclear power turbine, the annual average cold state starting times y of the type 1200MW nuclear power turbine is input based on a load database_cAnnual average temperature state starting times y_wAnnual average thermal state number of starts y_hNumber of normal annual stoppages y_nAnnual average 110% number of overspeed tests y₁₁₀Annual average operating hours t_yWorking speed n₀The results are shown in Table 1.

TABLE 1 number of starts and stops of steam turbine

Serial number	Item	Index value
				1	Number of cold-state annual starts y_cOnce/time	4
2	Number of annual mean temperature state starts y_wOnce/time	20
			3	Number of annual average thermal state starts y_hOnce/time	75
4	Number of annual average normal stops y_nOnce/time	99
			5	Annual average 110% number of overspeed tests y₁₁₀Once/time	1
6	Number of annual average operating hours t_y/h	7000
			7	Operating speed n₀/r/min	1500

S602, calculating first crack initiation life parameters of low cycle fatigue and high cycle fatigue of the nuclear turbine rotor.

Inputting design parameters of a nuclear turbine rotor, a three-dimensional mechanical model, centrifugal force, thermal load and gravity load of the nuclear turbine rotor and blades, and material performance data based on a component model database, a load database and a material database, determining a part with the maximum amplitude of high-cycle fatigue stress under a steady rated working condition as a weak part of the life 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 the cold start-stop low-cycle fatigue crack initiation life N of the weak part of the life of the nuclear turbine rotor_icLow cycle fatigue crack initiation life N at start and stop at temperature_iwThermal start-stop low cycle fatigue crack initiation life N_ihAnd a low cycle fatigue crack initiation life N in 110% overspeed test_i110And rotor high cycle fatigue crack initiation life N_iH。

For example, a part with the maximum amplitude of high cycle fatigue stress under the steady rated working condition is determined as a weak life part of the 1200MW nuclear power turbine rotor, the weak life part is a root circular angle part of an impeller at the steam exhaust side, and the cold start-stop low cycle fatigue crack initiation life N of the weak life part_icLow cycle fatigue crack initiation life N at start and stop at temperature_iwThermal start-stop low cycle fatigue crack initiation life N_ihAnd a low cycle fatigue crack initiation life N in 110% overspeed test_i110And rotor high cycle fatigue crack initiation life N_iHThe results are shown in Table 2.

TABLE 2 steam turbine rotor Low cycle fatigue and high cycle fatigue crack initiation Life N under the i-th operating mode_i

Serial number	Working conditions	Crack initiation life N_iOnce/time
			1	Cold start-stop low cycle fatigue	N_ic＝18900
2	Low cycle fatigue of starting, stopping and starting at warm state	N_iw＝20500
			3	Low cycle fatigue of hot start and stop	N_ih＝19900
4	110% overspeed test low cycle fatigue	N_i110＝6900
			5	High cycle fatigue in loaded operation	N_iH＝9.5×10⁹

S603, calculating a first crack propagation life parameter of the low cycle fatigue and the high cycle fatigue of the nuclear turbine rotor.

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 based on a component model database, a load database and a material database, and calculating to obtain a first-stage cold-start low-cycle fatigue crack extension life N of a 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_pc,1First stage warm start low cycle fatigue crack propagation life N_pw,1First stage hot start low cycle fatigue crack propagation life N_ph,1First stage normal shutdown low cycle fatigue crack propagation life N_pn,1First stage 110% overspeed test low cycle fatigue crack propagation life N_p110,1Second stage cold start low cycle fatigue crack propagation life N_pc,2Second stage warm start low cycle fatigue crack propagation life N_pw,2Second stage hot start low cycle fatigue crack propagation life N_ph,2Second stage normal shutdown low cycle fatigue crack propagation life N_pn,2110% overspeed test low cycle fatigue crack propagation life N_p110,2And rotor high cycle fatigue crack propagation life N_pH。

For example, the design parameters and the three-dimensional mechanical model of the 1200MW nuclear turbine rotor, the centrifugal force, the thermal load and the gravity load of the nuclear turbine rotor and the blades, and the material performance data are input, and the first-stage cold-starting low-cycle fatigue crack propagation life N of the weak part of the 1200MW nuclear turbine rotor is calculated by using the low-cycle fatigue and high-cycle fatigue life design monitoring method_pc,1First stage warm start low cycle fatigue crack propagation life N_pw,1First stage hot start low cycle fatigue crack propagation life N_ph,1First stage normal shutdown low cycle fatigue crack propagation life N_pn,1First stage 110% overspeed test low cycle fatigue crack propagation life N_p110,1Second stage cold start low cycle fatigue crack propagation life N_pc,2Second stage warm start low cycle fatigue crack propagation life N_pw,2Second stage hot start low cycle fatigue crack propagation life N_ph,1Second stage normal shutdown low cycle fatigue crack propagation life N_pn,2110% overspeed test low cycle fatigue crack propagation life N_p110,2And rotor high cycle fatigue crack propagation life N_pHThe results are shown in Table 3.

TABLE 3 rotor Low cycle fatigue and high cycle fatigue crack propagation life N_pi

And S604, calculating annual average high cycle fatigue times of the rotor of the nuclear turbine.

Annual average high cycle fatigue times y of nuclear turbine rotor_HCalculated according to the following formula:

wherein, t_yThe annual average operating hours of the nuclear turbine, n₀Is the working rotational speed.

For example, the annual average high cycle fatigue times y of the 1200MW nuclear turbine rotor_HCalculated according to the following formula:

in the above formula, t_y7000h, n for annual average operation hours of nuclear turbine₀The working speed is 1500 r/min.

And S605, calculating the total service life of the outer surface of the rotor of the nuclear turbine.

Total service life tau of outer surface of nuclear turbine rotor_CLtoCalculated according to the following formula:

for example, the weak part of the life of the rotor of the 1200MW nuclear power turbine is the root circular part of the impeller at the steam exhaust side, 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_CLtsCalculated according to the following formula:

and S606, calculating the total service life of the inner surface of the nuclear turbine rotor.

Total internal life τ of nuclear turbine rotor_CLtiCalculated according to the following formula:

for example, as the weak part of the life of the rotor of the 1200MW nuclear power turbine is the round corner part of the root of the impeller at the steam exhaust side, the weak part of the life is positioned on the outer surface of the rotor, tau_CLti＞τ_CLts。

And S607, determining the total service life of the nuclear turbine rotor.

Total life τ of a nuclear turbine rotor_CLtCalculated according to the following formula:

τ_CLt＝min{τ_CLto,τ_CLti}

for example, the total life tau of the 1200MW nuclear turbine rotor_CLtCalculated according to the following formula:

τ_CLt＝min{τ_CLts,τ_CLti}＝min{τ_CLts,τ_CLti＞τ_CLts}＝τ_CLts66.74 years old

And S608, performing operation optimization control on the low-cycle fatigue and high-cycle fatigue life of the nuclear turbine rotor.

The method for designing and monitoring the low-cycle fatigue and high-cycle fatigue life of the rotor of the nuclear turbine bearing centrifugal force, thermal load and gravity load is used for carrying out operation optimization control on the low-cycle fatigue and high-cycle fatigue life of the rotor of the nuclear turbine:

(1) if tau_CLtAnd (3) more than or equal to 60 years, the design monitoring of the low cycle fatigue and high cycle fatigue life of the nuclear turbine rotor bearing the centrifugal force, the thermal load and the gravity load is qualified, the design of the low cycle fatigue and high cycle fatigue life of the nuclear turbine rotor is in a controlled state, and the design monitoring of the low cycle fatigue and high cycle fatigue life of the nuclear turbine rotor is finished.

(2) If tau_CLtLess than 60 years, the design monitoring of the low cycle fatigue and the high cycle fatigue life of the rotor of the nuclear turbine bearing centrifugal force, thermal load and gravity load is unqualified, which shows that the design stage needs to change materials with better mechanical property, the operation optimization control improvement is carried out on the material design, the structure size, the structure fillet and the like, and S601 to S608 are executed again until tau is_CLtThe year is more than or equal to 60; for example, the low cycle fatigue and the high cycle fatigue life of the 1200MW nuclear turbine rotor are optimally controlled.

For example, due to τ_CLtThe design and monitoring of the low cycle fatigue and the high cycle fatigue life of the rotor of the 1200MW nuclear power turbine bearing centrifugal force, thermal load and gravity load are qualified when the year is 66.74 and is more than 60 years, which shows that the model 1200MW nuclear power turbine rotor bears the centrifugal force, the thermal load and the gravity loadThe design of the low-cycle fatigue and high-cycle fatigue life of the turbine rotor is in a controlled state, the design monitoring of the low-cycle fatigue and high-cycle fatigue life design of the 1200MW nuclear turbine rotor is finished, and the process of the design monitoring of the valve shell and the cylinder life is started.

According to the embodiment of the disclosure, the total service life of the rotor is obtained, and the rotor is optimally controlled when the total service life of the rotor does not meet the monitoring qualified condition, so that the service life of the rotor of the nuclear turbine can reach the qualified condition.

In a practical application scenario, when a valve casing and a cylinder of the nuclear power turbine bear pressure and heat load, the low-cycle fatigue life and the creep life of the nuclear power turbine are possibly damaged. Further, 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 under the action of pressure and thermal load for 60 years, which can be understood by referring to fig. 7, where fig. 7 is a schematic flow diagram of a method for monitoring the life of the nuclear turbine by using a combined monitoring platform of the nuclear turbine according to another embodiment of the present disclosure, and as shown in fig. 7, the method includes:

s701, determining the starting and stopping times of the nuclear turbine.

Method and subprogram for designing and monitoring low cycle fatigue and creep life of valve casing and cylinder of nuclear turbine based on load database and inputting annual cold-state starting times y of nuclear turbine_cAnnual average temperature state starting times y_wAnnual average thermal state number of starts y_hNumber of normal annual stoppages y_nAnnual average operating hours t_y。

For example, for a certain type 1200MW nuclear power turbine, the annual average cold state starting times y of the type 1200MW nuclear power turbine is input based on a load database_cAnnual average temperature state starting times y_wAnnual average thermal state number of starts y_hNumber of normal annual stoppages y_nAnnual average operating hours t_yThe results are shown in Table 4.

TABLE 4 number of starts and stops of steam turbine

S702, calculating second crack initiation life parameters of low-cycle fatigue and creep of a valve shell and a cylinder of the nuclear turbine.

Inputting design parameters and a three-dimensional mechanical model of the nuclear turbine and pressure and heat load of a valve shell and a cylinder of the nuclear turbine based on a component model database, a load database and a material database of the nuclear turbineAnd material performance data, determining the weak part of the service life of the valve shell and the cylinder of the nuclear turbine by using the low cycle fatigue and creep life design monitoring method and the subprogram, and calculating the cold start-stop low cycle fatigue crack initiation life N of the weak part of the service life of the valve shell and the cylinder of the nuclear turbine_cLow cycle fatigue crack initiation life N at start and stop at temperature_wThermal start-stop low cycle fatigue crack initiation life N_hAnd creep crack initiation life tau of valve housing and cylinder_c(ii) a Inlet temperature for pressurized water reactor nuclear steam turbine<The creep crack initiation life tau of the valve shell and the cylinder can not occur at 300 DEG C_cInfinity ∞ h, but the steam inlet temperature of the four-generation nuclear power turbine such as a high-temperature gas cooled reactor is more than 500 ℃, and the creep crack initiation life tau of the valve shell and the cylinder needs to be calculated_c。

For example, 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 1200MW nuclear turbine, pressure and heat load of a valve casing and a cylinder of the 1200MW nuclear turbine and material performance data, determining that the weak service life part of the valve casing and the cylinder of the 1200MW nuclear turbine is an inner cylinder outer surface steam inlet side steam inlet pipe and an inner cylinder transition fillet with the maximum transient stress by using a low cycle fatigue and creep life design monitoring method, and calculating to obtain the cold start-stop low cycle fatigue crack initiation life N of the weak service life part of the valve casing and the cylinder of the 1200MW nuclear turbine_cLow cycle fatigue crack initiation life N at start and stop at temperature_wThermal start-stop low cycle fatigue crack initiation life N_hThe results are shown in Table 5, since this model 1200MW nuclear turbine is a pressurized water reactor nuclear turbine, the admission temperature t is₀₁280.3 ℃, the creep crack initiation life tau of the weak part of the service life is processed without the creep deformation of the valve shell and the cylinder (however, for the four-generation nuclear power turbine such as high temperature gas cooled reactor, the steam inlet temperature is more than 500 ℃, the creep life damage is required to be considered), and the creep crack initiation life tau of the weak part of the service life is processed_cInfinite ∞ h; namely, the creep life accumulated loss of the weak part of the valve shell and the cylinder is 60 x 7000/tau_c＝0。

TABLE 5 Low cycle fatigue and creep crack initiation Life N of the steam turbine valve housing and Cylinder_i

And S703, calculating a second crack propagation life parameter of the valve shell and the cylinder low-cycle fatigue and creep 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 of the nuclear turbine, pressure and thermal load of a valve shell and a cylinder of the nuclear turbine and material performance data are input, and a low-cycle fatigue and creep life design monitoring method and a subprogram are used for calculating to obtain a cold-starting low-cycle fatigue crack extension life N of a weak life part of the valve shell and the cylinder of the nuclear turbine_fcLow cycle fatigue crack propagation life N for warm start_fwThermal start low cycle fatigue crack propagation life N_fhNormal shutdown low cycle fatigue crack propagation life N_fnAnd creep crack propagation life tau of valve housing and cylinder_fc(ii) a Inlet temperature for pressurized water reactor nuclear steam turbine<The creep of the valve shell and the cylinder can not occur at 300 ℃, and the creep crack is processed to extend the life tau_fcInfinity ∞ h, but the steam inlet temperature of the four-generation nuclear power turbine such as a high-temperature gas cooled reactor is more than 500 ℃, and the creep crack extension life tau of the valve shell and the cylinder needs to be calculated_fc。

For example, 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 model 1200MW nuclear turbine, the pressure and the thermal load of the valve casing and the cylinder of the model 1200MW nuclear turbine and material performance data are input, and the valve casing and the steam turbine casing of the model 1200MW nuclear turbine and the steam turbine are calculated by using a low-cycle fatigue and creep life design monitoring methodCold start low cycle fatigue crack propagation life N of cylinder weak part_fcLow cycle fatigue crack propagation life N for warm start_fwThermal start low cycle fatigue crack propagation life N_fhNormal shutdown low cycle fatigue crack propagation life N_fnThe results are given in Table 6 for inlet steam temperature of a pressurized water reactor nuclear steam turbine<The creep crack of the valve shell and the cylinder does not creep at 300 ℃, and the weak part of the service life of the valve shell and the cylinder is processed to expand the life tau_fcInfinite ∞ h (the steam inlet temperature of the four-generation nuclear power turbine such as a high-temperature gas cooled reactor is more than 500 ℃, and creep crack extension life tau of a valve shell and a cylinder needs to be calculated_fc)。

TABLE 6 Low cycle fatigue and creep crack propagation life N of weak part of steam turbine valve housing and cylinder_fi

Serial number	Working conditions	Crack initiation life N _fi
			1	Cold start-stop low cycle fatigue	N_fc1890 times
2	Low cycle fatigue of starting, stopping and starting at warm state	N_fh2310 times
			3	Low cycle fatigue of hot start and stop	N_fh3620 times
4	Operating creep under load	τ_fc＝∞h

And S704, calculating the total service life of the valve casing and the outer surface of the cylinder of the nuclear turbine.

Total service life tau of valve casing and outer surface of cylinder of nuclear turbine_CLtocCalculated according to the following formula:

for example, the total service life tau of the valve shell and the outer surface of the cylinder life weak part of the 1200MW nuclear power turbine_CLtocCalculated according to the following formula:

and S705, calculating the total service life of the valve shell of the nuclear turbine and the inner surface of the cylinder.

Total internal service life tau of valve casing and cylinder of nuclear turbine_CLticCalculated according to the following formula:

for example, the total internal life tau of the 1200MW nuclear power_CLticCalculated according to the following formula: the weak part of the service life of the valve shell and the cylinder of the 1200MW nuclear power turbine is the transition fillet of the steam inlet pipe and the inner cylinder at the steam inlet side of the outer surface of the inner cylinder with the largest transient stress, and the weak part of the service life is positioned on the outer surface of the inner cylinder, namely tau_CLtic＞τ_Cltoc。

And S706, determining the total service life of the valve casing and the cylinder of the nuclear turbine.

Total life tau of weak part of life of valve casing and cylinder of nuclear turbine_CLtCalculated according to the following formula:

τ_CLtc＝min{τ_CLtoc,τ_CLtic}

for example, the total life tau of the valve shell and the weak life part of the cylinder of the 1200MW nuclear power turbine_CLtcCalculated according to the following formula:

τ_CLtc＝min{τ_CLtoc,τ_CLtic}＝min{τ_CLtoc,τ_CLtic＞τ_CLtoc}＝τ_CLtoc75.07 years old

And S707, performing operation optimization control on the low-cycle fatigue and creep life of the valve shell and the cylinder of the nuclear turbine.

The method for monitoring the design of the low-cycle fatigue and the creep life of the pressure and the heat load of the nuclear turbine valve casing and the cylinder performs operation optimization control on the low-cycle fatigue and the creep life of the weak part of the service life of the nuclear turbine valve casing and the cylinder:

(1) if tau_CLtcAnd (4) more than or equal to 60 years, the design monitoring of the low-cycle fatigue and creep life of the pressure and the thermal load of the service life weak part of the valve casing and the cylinder of the nuclear turbine is qualified, the low-cycle fatigue and creep life design of the service life weak part of the valve casing and the cylinder of the nuclear turbine is in a controlled state, and the design monitoring of the low-cycle fatigue and creep life design of the service life weak part of the valve casing and the cylinder of the nuclear turbine is finished.

(2) If tau_CLtAnd (5) less than 60 years, the design monitoring of the low-cycle fatigue and creep life of the pressure and heat load of the service-life weak part of the valve shell and the cylinder of the nuclear turbine is unqualified, which shows that the material with better mechanical property needs to be changed in the design stage, the operation optimization control improvement is carried out on the material design, the structure size, the structure fillet and the like, and S701 to S707 are executed again until tau is zero_CLtcNot less than 60 years.

For example, the low cycle fatigue and creep life of the valve casing and the weak life part of the cylinder of the 1200MW nuclear turbine are optimally controlled.

Due to tau_CLtc75.07 years oldThe pressure of the service life weak part of the valve casing and the cylinder of the 1200MW nuclear turbine is qualified with the design monitoring of the low-cycle fatigue and creep life of the thermal load, which indicates that the design of the low-cycle fatigue and creep life of the service life weak part of the valve casing and the cylinder of the 1200MW nuclear turbine is in a controlled state, the design monitoring of the low-cycle fatigue and creep life of the service life weak part of the valve casing and the cylinder of the 1200MW nuclear turbine is finished, and the process that the rotor, the valve casing and the cylinder bear the rapid starting thermal stress and the service life reaches 60 years of operation monitoring can be entered.

The total service life of the valve casing and the cylinder is obtained in the embodiment of the disclosure, and the operation optimization control is performed on the valve casing and the cylinder when the total service life of the valve casing and the cylinder does not meet the monitoring qualified condition, so that the service life of the valve casing and the cylinder of the nuclear power steam turbine can reach the qualified condition.

In practical application scenarios, when the rotor, the valve casing and the cylinder of the nuclear power turbine bear the action of rapid starting thermal stress, the service life of the nuclear power turbine is possibly damaged. Further, the long-life design monitoring can be performed on the rotor, the valve casing and the cylinder of the nuclear turbine which bear the rapid-start thermal stress action for a long life of 60 years, which can be understood by referring to fig. 8, where fig. 8 is a schematic flow chart of a method for monitoring the life of the nuclear turbine by using a combined monitoring platform of the nuclear turbine according to another embodiment of the present disclosure, and as shown in fig. 8, the method includes:

s801, calculating thermal stress monitoring parameters of the rotor, the valve shell and the cylinder which bear the rapid starting thermal stress.

Based on a component model database, a load database and a material database of the 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, design parameters of a rotor, the valve casing and the cylinder of the nuclear turbine, three-dimensional mechanical model and material mechanical property data, and calculating the thermal stress sigma corresponding to the 60-year service life of the rotor of the nuclear turbine by using a method and a subprogram for monitoring the rapid starting of the rotor, the valve casing and the cylinder_thrThe valve casing of the nuclear turbine corresponds to 60 yearsThermal stress of lifetime σ_thvThermal stress sigma corresponding to 60-year service life of nuclear turbine cylinder_thcAnd the volume average temperature t of the rotor of the nuclear turbine during starting, stopping or running_miThe simulation value of (1).

For example, for a certain model 1200MW nuclear turbine, 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 casing and a cylinder, the metal temperature of a measuring point at a depth of 45% -50% of the wall thickness of the valve casing and the cylinder, design parameters of a rotor, the valve casing and the cylinder of the nuclear turbine, and three-dimensional mechanical model and material mechanical property data are input, and a method for monitoring the rapid starting excessive thermal stress borne by the rotor, the valve casing and the cylinder is used for calculating the thermal stress sigma corresponding to the 60-year life of the rotor of the model 1200MW nuclear turbine_thr692MPa, the thermal stress sigma of the valve shell of the nuclear turbine corresponding to 60 years of service life_thv458MPa, the thermal stress sigma of the nuclear turbine cylinder corresponding to the 60-year service life_thc463MPa, and simulated value t of the mean temperature of the rotor volume of the nuclear turbine during starting, stopping or running_mi＝100℃。

S802, calculating the volume average temperature difference of the nuclear turbine rotor on line.

Calculating the average temperature difference delta t of the volume of the rotor of the nuclear turbine on line according to the online monitoring value of the metal temperature of the inner cylinder of the nuclear turbine_mrCalculated according to the following formula:

Δt_mr＝|t_mi-t₉₅|

wherein, t_miIs a simulated value of the mean temperature of the rotor volume during the start-up process, t₉₅The metal temperature of a point measured at the depth of 85% -95% of the wall thickness of an inner cylinder of the nuclear turbine.

For example, the metal temperature on-line monitoring value t of the inner cylinder of the 1200MW nuclear power turbine₉₅The mean temperature difference delta t of the rotor volume of the 1200MW nuclear power turbine is calculated on line at 270 DEG C_mrCalculated according to the following formula:

Δt_mr＝|t_mi-t₉₅|＝|100-270|＝170℃

in the above formula, t_miIs a simulated value of the rotor volume mean temperature during the start-up process of 100 DEG C₉₅The metal temperature of a point at the depth of 85-95% of the wall thickness of an inner cylinder of the nuclear turbine is measured, and the metal temperature of the point at the depth of 95% of the wall thickness of the inner cylinder is 270 ℃.

And S803, calculating the mean temperature difference of the nuclear turbine valve shell on line.

Calculating the mean temperature difference delta t of the valve shell of the nuclear turbine on line according to the online metal temperature monitoring value of the steam inlet valve shell of the nuclear turbine_mvCalculated according to the following formula:

Δt_mv＝|t_50v-t_95v|

for example, the model 1200MW nuclear turbine inlet valve casing metal temperature on-line monitoring value t₉₅271 ℃ and t₅₀The mean temperature difference delta t of the valve shell product of the 1200MW nuclear power turbine is calculated on line at 138 DEG C_mvCalculated according to the following formula:

Δt_mv＝|t_50v-t_95v|＝|138-271|＝133℃

in the above formula, t_50vThe temperature of the metal measured at the point with the depth of 45-50% of the wall thickness of the valve shell is 138 ℃, t_95vThe metal temperature of the point at the depth of 85% -95% of the wall thickness of the valve shell is measured, and the metal temperature of the point at the depth of 95% of the wall thickness of the valve shell is measured at 271 ℃.

S804, calculating the volume average temperature difference of the cylinder of the nuclear turbine on line.

According to the metal temperature on-line monitoring value of the nuclear turbine cylinder, the volume average temperature difference delta t of the nuclear turbine cylinder is calculated on line_mcCalculated according to the following formula:

Δt_mc＝|t_50c-t_95c|

for example, the model 1200MW nuclear turbine cylinder metal temperature on-line monitoring value t₉₅240 ℃ and t₅₀130 ℃, and calculating the volume average temperature difference delta t of the cylinder of the 1200MW nuclear power turbine on line_mcAs followsCalculating by the formula:

Δt_mc＝|t_50c-t_95c|＝|130-240|＝110℃

in the above formula, t_50cThe temperature of the metal at the measuring point at the depth of 45-50% of the wall thickness of the cylinder is measured at 130 ℃ t_95cThe metal temperature of the measuring point at the depth of 85% -95% of the wall thickness of the cylinder is 240 ℃ in the embodiment, namely the metal temperature of the measuring point at the depth of 95% of the wall thickness of the cylinder is measured.

S805, calculating the temperature difference ratio of the nuclear turbine rotor on line.

Temperature difference ratio R of nuclear turbine rotor_ΔtrCalculated according to the following formula:

wherein, Δ t_mrIs the mean temperature difference of the rotor volume, 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_thrThe thermal stress of the nuclear turbine rotor corresponding to the service life of 60 years.

For example, the temperature difference ratio R of the rotor of the 1200MW nuclear turbine_ΔtrCalculated according to the following formula:

in the above formula,. DELTA.t_mrThe mean temperature difference of the rotor volume is 170 ℃, and E is the elastic modulus of the rotor material at the working temperature is 1.912 multiplied by 10⁵MPa and beta are the linear expansion coefficient of the rotor material at the working temperature of 12.62 multiplied by 10^-6(1/K), mu is the Poisson's ratio of the rotor material at the working temperature of 0.303, sigma_thrThe thermal stress 692Mpa corresponds to the nuclear turbine rotor with the service life of 60 years.

And S806, calculating the temperature difference ratio of the valve casing of the nuclear turbine on line.

Nuclear power steam turbine valve casing temperature difference ratio R_ΔtvCalculated according to the following formula:

wherein, Δ t_mvThe mean temperature difference of the valve shell, 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's ratio of the valve shell material at the working temperature, and sigma is_thvThe thermal stress of the nuclear turbine valve casing corresponding to the 60-year service life is provided.

For example, the valve casing temperature difference ratio R of the 1200MW nuclear turbine_ΔtvCalculated according to the following formula:

in the above formula,. DELTA.t_mvThe mean temperature difference of the valve shell is 133 ℃, and E is the elastic modulus of the valve shell material at the working temperature of 1.994 multiplied by 10⁵MPa and beta is the linear expansion coefficient of the valve shell material at the working temperature of 12.71 multiplied by 10^-6(1/K), mu is the Poisson's ratio of the valve housing material at the working temperature of 0.28, sigma_thvThe thermal stress is 458Mpa corresponding to the service life of 60 years of a nuclear turbine valve casing.

S807, calculating the temperature difference ratio of the nuclear turbine cylinder on line.

Temperature difference ratio R of nuclear turbine cylinder_ΔtcCalculated according to the following formula:

wherein, Δ t_mcIs the mean temperature difference of 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_thcThe thermal stress of the nuclear turbine cylinder corresponding to the 60-year service life is achieved.

For example, the model 1200Temperature difference ratio R of cylinder of MW nuclear power turbine_ΔtcCalculated according to the following formula:

in the above formula,. DELTA.t_mcThe average temperature difference of the cylinder volume is 110 ℃, and E is the elastic modulus of the cylinder material at the working temperature is 1.974 multiplied by 10⁵MPa and beta is the linear expansion coefficient of the cylinder material at the working temperature of 13.00 multiplied by 10^-6(1/K), mu is the Poisson's ratio of the cylinder material at the working temperature of 0.28, sigma_thcThe thermal stress of a nuclear turbine cylinder corresponding to the 60-year service life is 463 Mpa.

And S808, determining the maximum temperature difference ratio of the nuclear turbine.

Maximum temperature difference ratio R of nuclear turbine_ΔtmaxCalculated according to the following formula:

R_Δtmax＝{R_Δtr,R_Δtv,R_Δtc}

for example, the maximum temperature difference ratio R of the 1200MW nuclear turbine_ΔtmaxCalculated according to the following formula:

R_Δtmax＝{R_Δtr,R_Δtv,R_Δtc}＝{0.885，1.022，0.847}＝1.022

and S809, performing life operation optimization control on the rotor, the valve shell and the cylinder under the action of the quick starting thermal stress.

Through the life monitoring method that the nuclear power steam turbine rotor, the valve casing and the cylinder bear the action of quick start thermal stress, the life that the nuclear power steam turbine rotor, the valve casing and the cylinder bear the action of quick start overlarge thermal stress is operated and optimized to be controlled:

(1) if R is_ΔtmaxAnd (3) the service life of the rotor, the valve casing and the cylinder of the nuclear turbine bearing the rapid starting thermal stress is monitored to be qualified, and the service life of the rotor, the valve casing and the cylinder bearing the rapid starting thermal stress is in a controlled state.

(2) If R is_ΔtmaxNot less than 1, the service life of the rotor, the valve casing and the cylinder of the nuclear turbine bearing the quick starting thermal stressUnqualified life monitoring shows that the starting process of the nuclear turbine needs to be optimized and improved in the operation stage, the change rate of the steam inlet temperature of the nuclear turbine is reduced to 0.5-0.8 time of the current change rate, and S801-S808 are executed again until R_ΔtmaxUntil less than 1.

For example, the operation optimization control is carried out on the service life of the rotor, the valve casing and the cylinder of the 1200MW nuclear turbine which bear the action of quick start and overlarge thermal stress:

due to R_ΔtmaxThe service life monitoring that the rotor, the valve casing and the cylinder of the 1200MW nuclear turbine bear the action of quick starting thermal stress is unqualified, which indicates that the starting process of the 1200MW nuclear turbine needs to be optimized and improved in the operation stage, the change rate of the steam inlet temperature of the 1200MW nuclear turbine is reduced to 0.6 time of the current temperature, S801 to S808 are executed again, and the monitoring result is listed in 7; at this time R_ΔtmaxIf the frequency is less than 1, the service life of the rotor, the valve casing and the cylinder of the 1200MW nuclear turbine bearing the rapid starting thermal stress is qualified, and the service life of the rotor, the valve casing and the cylinder bearing the rapid starting thermal stress is in a controlled state.

TABLE 7 operation monitoring of a nuclear turbine subjected to rapid start thermal stress

Step (ii) of	Item	The ith operation monitor	The (i + 1) th operation monitor
				801	Rotor volume average temperature simulation value	t_mi＝100℃	t_mi＝103℃
802	Mean temperature difference of rotor volume	Δt_mr＝170℃	Δt_mr＝159℃
				803	Valve housing volume average temperature difference	Δt_mv＝133℃	Δt_mv＝117℃
804	Mean temperature difference of cylinder volume	Δt_mc＝110℃	Δt_mc＝102℃
				805	Rotor temperature difference ratio	R_Δtr＝0.885	R_Δtr＝0.796
806	Valve housing temperature difference ratio	R_Δtv＝1.022	R_Δtv＝0.877
				807	Temperature difference ratio of cylinder	R_Δtc＝0.847	R_Δtc＝0.785
808	Maximum temperature difference ratio of nuclear turbine	R_Δtmax＝1.022	R_Δtmax＝0.877
				809	Life operating optimization control	Unqualified monitoring of service life	The service life is qualified by monitoring

According to the embodiment of the disclosure, the maximum temperature difference ratio of the nuclear turbine is obtained, and the operation optimization control is performed on the starting process when the temperature difference ratio does not meet the monitoring qualified condition, 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 of a nuclear power turbine provided by the present disclosure can implement safety monitoring of the nuclear power turbine, which can be further understood with reference to fig. 9, where fig. 9 is a schematic flow diagram of a monitoring method of a combined monitoring platform of a nuclear power turbine according to another embodiment of the present disclosure, and 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 for the nuclear turbine, and according to the received safety monitoring instruction, the combined monitoring platform of the nuclear turbine can perform safety monitoring on the nuclear turbine.

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 operation state, the load borne by the nuclear turbine 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 operation 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, acquiring at least one of the following data based on the running state data and the load data matched with the safety monitoring instruction and the material performance data:

acquiring first intensity safety monitoring data of power reduction and stress corrosion caused by scaling, abrasion, corrosion and water erosion damage borne by a nuclear turbine;

acquiring second intensity safety monitoring data of steady state and transient state of a rotor of the nuclear turbine under the action of centrifugal force and thermal load;

acquiring third intensity safety monitoring data of steady state and transient state of the pressure and heat load bearing action of a valve shell and a cylinder of the nuclear turbine;

acquiring safety design monitoring data and safety operation monitoring data of a flange median plane under the action of bearing force load, thermal load and bolt pretightening force load of a cylinder of the nuclear turbine;

and determining the first intensity safety monitoring data, the second intensity safety monitoring data, the third intensity safety monitoring data, the safety design monitoring data and the safety operation monitoring data as the safety monitoring data of the nuclear power turbine.

In the operation process of the nuclear turbine, partial components exist, and relevant attribute parameters such as the operation state, the load bearing effect, the material performance and the like of the components are greatly related to the safe operation of the nuclear turbine.

Therefore, the data processing server can acquire at least one of the operation state data, the load data and the material performance data matched with the safety monitoring instruction as corresponding safety monitoring data based on the safety monitoring instruction.

Optionally, first intensity safety monitoring data of the nuclear turbine subjected to scaling, abrasion, corrosion and water erosion damage resulting in power drop and stress corrosion is obtained.

In the embodiment of the disclosure, the operating process of the nuclear turbine may have the possibility of bearing scaling, abrasion, corrosion and water erosion damage, so that the nuclear turbine has the possibility of power reduction and stress corrosion.

Therefore, the data processing server can obtain at least one of running state data, load data and material performance data matched with the state of the nuclear turbine subjected to scaling, abrasion, corrosion and water erosion damage from a database connected with the data processing server, serve as safety monitoring data matched with the safety monitoring instruction, and determine the safety monitoring data as first strength safety monitoring data of the nuclear turbine.

Optionally, second intensity safety monitoring data of steady state and transient state of the rotor of the nuclear turbine bearing 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 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 embodied by the steady state strength and the transient state strength of the rotor.

In the implementation, when the rotor of the nuclear turbine bears the action of 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 intensity data and transient intensity data.

Further, steady-state intensity data and transient intensity data of the rotor of the nuclear turbine under the action of centrifugal force and thermal load can be obtained and determined as second intensity safety monitoring data.

Optionally, third intensity safety monitoring data of steady state and transient state of the pressure and thermal load bearing effect of the valve casing and the cylinder of the nuclear turbine are obtained.

In the embodiment of the disclosure, the valve casing and the cylinder of the nuclear turbine are in certain association with the safe operation of the nuclear turbine, wherein the safety of the valve casing and the cylinder can be embodied by the transient strength and the steady strength of the valve casing and the cylinder.

In the operation process of the nuclear turbine, the valve shell and the cylinder have the possibility of bearing the pressure and the heat load. Accordingly, the safety of the valve housing and cylinder is affected to some extent when subjected to pressure and thermal loads. This in turn leads to the possibility of changes in the transient and steady state strength of the valve housing and cylinder when subjected to pressure and thermal loads.

Further, steady state and transient strength data of the valve housing and cylinder under pressure and thermal loading may be obtained and determined as third strength safety monitoring data.

Optionally, safety design monitoring data and safety operation monitoring data of a flange middle section of a nuclear turbine under the action of bearing force load, thermal load and bolt pretightening force load are obtained.

In the implementation, the related state of the flange bisection of the cylinder of the nuclear turbine has certain influence on the safe operation of the nuclear turbine. When the tightness of the flange split surface of the cylinder is damaged, steam leakage of the flange split surface may occur.

The related state of the split surface of the flange can be influenced to a certain degree when the cylinder bears load, thermal load and bolt pretightening force load.

Therefore, when the cylinder of the nuclear turbine bears the force load, the heat load and the bolt pretightening force load, the related data of the tightness of the cylinder flange bisection can be obtained and used as the corresponding monitoring data.

Optionally, the tightness of the cylinder flange midplanes may be embodied based on the safety design data and the safety operation data of the cylinder flange midplanes, and therefore, the safety design data and the safety operation data of the cylinder flange midplanes may be used as the monitoring data matched with the safety monitoring instruction.

Further, when the cylinder of the nuclear turbine bears the force load, the heat load and the bolt pretightening force load, safety design data and safety operation data of the cylinder flange bisection are determined as safety design monitoring data and safety operation monitoring data.

Optionally, the first intensity safety monitoring data, the second intensity safety monitoring data, the third intensity safety monitoring data, the safety design monitoring data and the safety operation monitoring data are determined as safety monitoring data of the nuclear turbine.

In the embodiment of the disclosure, the safety monitoring requirement of the nuclear turbine can be covered by the first strength safety monitoring data, the second strength safety monitoring data, the third strength safety monitoring data, the safety design monitoring data and the safety operation monitoring data.

Therefore, the first intensity safety monitoring data, the second intensity safety monitoring data, the third intensity safety monitoring data, the safety design monitoring data and the safety operation monitoring data can be determined as the safety monitoring data of the nuclear turbine.

According to the combined monitoring platform of the nuclear turbine, safety monitoring is carried out 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 is obtained from a corresponding database, and then the safety monitoring data of the nuclear turbine matched with the safety monitoring instruction are determined. According to the method and the device, the safety monitoring of the steam turbine is realized through the safety monitoring data, the safety monitoring effect of the nuclear steam turbine is optimized, and the high-safety monitoring of the nuclear steam turbine is realized.

In order to better understand the embodiments, the implementation of the safety monitoring performed on 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 may be further combined with the following embodiments.

In practical application scenarios, when a nuclear turbine is subjected to scaling, abrasion, corrosion and water erosion, the possibility of power reduction and stress corrosion exists. Further, safety design monitoring can be performed on power reduction and stress corrosion strength when the nuclear turbine is subjected to scaling, abrasion, corrosion and water erosion damage, which can be understood by referring to fig. 10, where fig. 10 is a schematic flow chart of a method for monitoring safety of a nuclear turbine by using a combined monitoring platform of a nuclear turbine according to an embodiment of the present disclosure, and as shown in fig. 10, the method includes:

and S1001, calculating the flow ratio of the nuclear turbine.

Inputting the steam inlet pressure, the steam inlet temperature and the steam exhaust pressure of a newly designed nuclear turbine, and putting the nuclear turbine into operation₀1500r/min, the steam inlet parameter and the steam exhaust pressure of the nuclear turbine are calculated to obtain the isentropic enthalpy drop H of the newly designed nuclear turbine rated working condition based on the thermodynamic parameters of the nuclear turbine and the method and the subprogram for safely designing and monitoring the power drop and the stress corrosion strength of the power drop and the stress corrosion damage of the scaling, abrasion and corrosion damage under the conditions of different steam inlet parameters and the same working speed_s1Isentropic enthalpy drop H of rated working condition of put-into-operation nuclear turbine_s01Electric power N of a nuclear turbine_eConstant flow rate G, isentropic enthalpy drop H_sInternal efficiency eta of steam turbine_0iMechanical efficiency eta_mEfficiency eta of the generator_gHas a relation of N_e＝G×H_s1×η_0i×η_m×η_gAt a relative internal efficiency η_0iMechanical efficiency eta_mAnd generator efficiency η_gSame and electric power N_eUnder the condition that the difference is within 50%, newly designed flow G of the nuclear turbine₁And has already been put into operationNuclear turbine flow G₀₁Flow rate ratio F_R1The calculation formula of (2) is as follows:

wherein G is₁For newly designing flow rate of rated working condition of nuclear turbine G₀₁The flow rate of the operating nuclear turbine with electric power difference of more than 50 percent under rated working condition, N_e1For newly designing electric power of rated working condition of nuclear turbine, N_e01For electric power of rated condition of already put into operation nuclear turbine, P_cfFor newly designed nuclear steam turbines to withstand the power reduction coefficient of scaling, wear and corrosion damage, preferably, P_cf＝1.01～1.03。

For example, the inlet pressure p of the 1200MW nuclear turbine is input₀₁6.45MPa, steam admission temperature t₀₁280.3 ℃ and exhaust pressure p_k15.78kPa, 1087MW nuclear power turbine inlet pressure p has been put into operation₀6.45MPa, steam admission temperature t₀280.3 deg.C, exhaust pressure p_k5.78kPa and the same operating speed n₀1500r/min, and calculating to obtain the isentropic enthalpy drop H of the newly designed rated working condition of the 1200MW nuclear power turbine by using a method and a subprogram for safely designing and monitoring the power drop and the stress corrosion strength of the scale formation, the abrasion and the corrosion damage based on the thermodynamic parameters of the 1200MW nuclear power turbine_s1Equal entropy enthalpy drop H between 950.90kJ/kg and the rated working condition of 1087MW nuclear power turbine already put into operation_s01952.28 kJ/kg. Electric power N of nuclear turbine_eConstant flow rate G, isentropic enthalpy drop H_sInternal efficiency eta of steam turbine_0iMechanical efficiency eta_mEfficiency eta of the generator_gHas a relation of N_e＝G×H_s1×η_0i×η_m×η_gAt a relative internal efficiency η_0iMechanical efficiency eta_mAnd generator efficiency η_gSame and electric power N_eUnder the condition that the difference is more than 50%, the flow G of the 1200MW nuclear power turbine is newly designed₁And has already been put into operation1087MW nuclear turbine flow G₀₁Flow rate ratio F_R1The calculation formula of (2) is as follows:

in the above formula, G₁For newly designing the flow of the rated working condition G of a 1200MW nuclear turbine₀₁The electric power phase difference (1200-power 1087)/1087-10.4 percent) is the flow rate of the 1087MW nuclear power turbine which is already put into operation under the rated working condition<50％，N_e1The electric power of the rated working condition of the nuclear turbine is 1200MW, N for new design_e01Electric power 1087MW, P for rated working condition of put into operation nuclear power turbine_cfFor newly designed nuclear steam turbines to withstand the power reduction coefficient of scaling, wear and corrosion damage, preferably, P_cf1.01 to 1.03, in this example, P is taken_cf＝1.02。

S1002, determining the flow of the nuclear turbine.

The existing flow G at each level of rated working condition of the put-into-service nuclear turbine with electric power difference within 50%_0iFor ensuring the power of the turbine, the flow rates G of the stages of the turbine_iThe calculation formula of (2) is as follows:

G_i＝G_0i×F_R1

wherein, F_R1Is the flow ratio of the nuclear turbine.

For example, the existing flow G of each stage of the rated working condition of the 1087MW nuclear power turbine which has been put into operation and has the electric power difference within 50 percent_0iIn order to ensure the power of a newly designed 1200MW nuclear turbine, the flow G of each stage of the 1200MW nuclear turbine is_iThe calculation formula of (2) is as follows:

G_i＝G_0i×F_R1＝1.127669G_0i

in the above formula, F_R1Is the flow ratio of the nuclear turbine.

S1003, determining the modeling ratio of the nuclear turbine.

Flow ratio F of known nuclear turbine_R1Modelling of nuclear turbinesRatio of S_FThe calculation formula of (2) is as follows:

for example, the flow ratio F of a 1200MW nuclear turbine is known_R1The modeling ratio S of the 1200MW nuclear turbine_FThe calculation formula of (2) is as follows:

and S1004, performing modeling amplification on the size of the nuclear turbine component.

The structural design of the nuclear power turbine adopts a modeling design method on the basis of the put-into-operation nuclear power turbine, and the existing main structural size of the put-into-operation nuclear power turbine with the electric power difference within 50 percent is multiplied by the modeling ratio S of the nuclear power turbine_FAnd obtaining the main structural size of the newly designed nuclear turbine.

For example, the structural design of the model 1200MW nuclear power turbine is based on the commissioning of a 1087MW nuclear power turbine, and the main structural dimensions of the commissioning 1087MW nuclear power turbine with an electric power difference of less than 50% are multiplied by the modeling ratio S of the model 1200MW nuclear power turbine_FAnd obtaining the main structural size of the newly designed 1200MW nuclear power turbine.

S1005, calculating the safety design quantity of the stress corrosion damage of the nuclear turbine rotor and the blade root.

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 to obtain the maximum principal stress sigma of a contact wet steam surface of the nuclear turbine rotor or the blade root under a steady rated working condition by using a method and a subprogram for safely designing and monitoring power reduction and stress corrosion strength of the nuclear turbine rotor and the blade root which bear scaling, abrasion, corrosion and water erosion damage₁Calling the yield limit of the material at the working temperature t in the material database

For example, the design parameters and the three-dimensional mechanical model of the 1200MW nuclear power turbine rotor and the blade root, the centrifugal force and the thermal load of the nuclear power turbine rotor and the blade root, and the material performance data are input, and the maximum principal stress sigma of the contact wet steam surface of the blade root groove of the 1200MW nuclear power turbine rotor under the steady rated working condition is calculated by using the method and the subprogram for safely designing and monitoring the power reduction and the stress corrosion strength which bear scaling, abrasion, corrosion and water erosion damage₁432MPa, and the yield limit of the rotor material at the working temperature t of 100 ℃ in the material database is called

S1006, calculating the maximum main stress ratio of the nuclear turbine rotor and the blade root under the steady rated working condition.

Maximum main stress ratio R of contact wet steam surface of nuclear turbine rotor and blade root under steady rated working condition_σ1Calculated according to the following formula:

wherein σ₁The maximum main stress of the contact wet steam surface of the rotor or the blade root of the nuclear turbine under the stable rated working condition,

is the yield limit of the material at the operating temperature.

For example, the maximum main stress ratio R of the contact wet steam surface of the rotor and the blade root of the 1200MW nuclear power turbine under the steady rated working condition_σ1Calculated according to the following formula:

in the above formula, σ₁The maximum main stress of the contact wet steam surface of the nuclear turbine rotor or blade root under the stable rated working condition is 432MPa,

the yield limit of the rotor material at the working temperature of 100 ℃ is 640 MPa.

S1007, optimally controlling the operation of the stress corrosion strength of the nuclear turbine rotor and the blade root.

The method for monitoring the power reduction and stress corrosion strength safety design of the scaling, abrasion and corrosion damage borne by the nuclear turbine is used for carrying out operation optimization control on the stress corrosion strength of a rotor and a 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_σ1Not less than 0.7, unqualified safety design monitoring of stress corrosion damage of the nuclear turbine rotor and the blade root shows that a material with better mechanical property needs to be changed in the design stage, operation optimization control improvement is carried out on material design, structure size, wall thickness, structure fillet and the like, and S1005 to S1007 are executed again until R_σ1<Up to 0.7;

for example, by a design monitoring method of the safety of stress corrosion damage of the nuclear turbine rotor and the blade root, the operation optimization control is performed on the stress corrosion strength of the 1200MW nuclear turbine rotor and the blade root.

Due to R_σ1＝0.675<0.7, the safety design monitoring of the stress corrosion damage of the rotor and the blade root of the 1200MW nuclear turbine is qualified, which shows that the stress corrosion damage of the rotor and the blade root of the 1200MW nuclear turbine is in a controlled state, and the design monitoring of the stress corrosion damage of the rotor and the blade root of the 1200MW nuclear turbine is finished.

In the embodiment of the disclosure, the maximum principal stress ratio of the rotor and the blade root of the nuclear turbine under the steady-state rated working condition meets the monitoring qualified 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 an actual application scenario, when a cylinder of the nuclear power turbine bears a force load, a thermal load and a bolt pretightening force load, the split tightness of a flange of the cylinder may be affected. The safety design monitoring can be performed on the split tightness of the flange of the cylinder of the nuclear turbine under the action of bearing force load, thermal load and bolt pretightening force load, which can be understood by combining fig. 11, where fig. 11 is a schematic flow chart of a safety monitoring method of a nuclear turbine by a nuclear turbine combined monitoring platform according to another embodiment of the present disclosure, and as shown in fig. 11, the method includes:

s1101, calculating the cylinder flange median tightness design quantity.

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 of a cylinder of the nuclear turbine, pressure and thermal load of the cylinder, bolt pre-tightening force load and material performance data are input, a method and a subprogram for designing and monitoring the split tightness in a flange under the action of the bearing force load, the thermal load and the bolt pre-tightening force load of the cylinder are used, and a split maximum opening penetration gap c in the flange of the cylinder of the nuclear turbine is calculated_op(mm) minimum contact stress σ with the flange mid-plane of the cylinder_cs。

For example, based on a component model database, a load database and a material database of a nuclear turbine, inputting design parameters and a three-dimensional mechanical model of a 1200MW nuclear turbine cylinder, pressure and heat load of the cylinder, bolt pre-tightening force load and material performance data, using a method and a subprogram for designing and monitoring the bisection tightness of a cylinder flange, wherein a single-layer cylinder is adopted in a high-pressure cylinder of the 1200MW nuclear turbine, and a maximum opening penetration gap c of a bisection surface of the flange of the 1200MW nuclear turbine cylinder is calculated_op0.03mm and minimum contact stress sigma of flange split surface of cylinder_cs＝14.51MPa。

S1102, calculating the pressure difference between the inner surface and the outer surface of the flange split surface of the nuclear turbine cylinder.

The pressure difference delta P of the inner surface and the outer surface of the split surface in the flange of the nuclear turbine cylinder is calculated according to the following formula:

ΔP＝P_i-P_o

wherein, P_iMaximum steam pressure, P, of the cylinder inner surface_oCylinder outer surface fluid pressure.

For example, the pressure difference Δ P between the inner surface and the outer surface of the split surface in the flange of the nuclear turbine cylinder is calculated according to the following formula:

ΔP＝P_i-P_o＝6.45-0.10＝6.35MPa

in the above formula, P_iThe maximum steam pressure of the inner surface of the cylinder is 6.45MPa, P_oThe atmospheric pressure of the outer surface of the cylinder is 0.10 MPa.

S1103, calculating the ratio of the opening penetration gaps of the middle planes of the flanges of the nuclear turbine cylinder.

Flange mid-span opening penetration gap ratio R of nuclear turbine cylinder_copCalculated according to the following formula:

wherein, c_opIs a penetration gap of a split opening in a flange of a nuclear turbine cylinder.

For example, the ratio R of the split penetration clearance of the flange of the 1200MW nuclear turbine cylinder_copCalculated according to the following formula:

s1104, calculating the contact stress ratio of the split surfaces of the flange of the nuclear turbine cylinder.

Flange mid-split contact stress ratio R of nuclear turbine cylinder_σcsCalculated according to the following formula:

wherein σ_csIs the flange mid-section contact stress of the nuclear turbine cylinder, and the delta P is the pressure difference between the inner surface and the outer surface of the nuclear turbine cylinder.

For example, the flange median plane contact stress ratio R of the 1200MW nuclear turbine cylinder_σcsCalculated according to the following formula:

s1105, the operation of the split opening in the flange of the nuclear turbine cylinder is optimized and controlled.

The method for monitoring the tightness of the flange bisection surface by the effects of bearing force load, thermal load and bolt pretightening force load of the nuclear turbine cylinder performs operation optimization control on the flange bisection surface opening of the nuclear turbine cylinder:

(1) if R is_copAnd (3) less than 1, the design monitoring of the flange middle split opening of the nuclear turbine cylinder is qualified, which shows that the flange middle split opening of the nuclear turbine cylinder is in a controlled state, and the design monitoring of the flange middle split opening of the nuclear turbine cylinder is finished.

(2) If R is_copAnd (3) not less than 1, unqualified design monitoring of the split opening in the flange of the nuclear turbine cylinder indicates that operation optimization control improvement needs to be carried out on the flange size, the number of bolts, the bolt diameter, the bolt material, the bolt pre-tightening force and the like in the design stage, and S1101 to S1105 are executed again until R_copUntil less than 1.

For example, the operation optimization control is carried out on the flange bisection opening of the 1200MW nuclear power turbine cylinder by a flange bisection tightness design monitoring method under the action of bearing force load, thermal load and bolt pretightening force load of the nuclear power turbine cylinder.

Due to R_copThe design and the monitoring of the split opening in the flange of the 1200MW nuclear turbine cylinder are qualified, which indicates that the nuclear turbine cylinder is 0.300 & lt 1The opening of the middle section of the flange is in a controlled state, and the design monitoring of the opening of the middle section of the flange of the 1200MW nuclear power turbine cylinder is finished.

And S1106, optimally controlling the operation of the split contact stress in the flange of the nuclear turbine cylinder.

By the method for monitoring the flange bisection surface tightness under the action of bearing force load, thermal load and bolt pretightening force load of the nuclear turbine cylinder, the operation optimization control is performed on the flange bisection surface contact stress of the nuclear turbine cylinder:

(1) if R is_σcsAnd (4) if the design and the monitoring of the contact stress of the flange median plane of the nuclear turbine cylinder are qualified, the flange median plane contact stress of the cylinder is in a controlled state, and the design and the monitoring of the flange median plane contact stress of the nuclear turbine cylinder are finished.

(2) If R is_σcsThe design monitoring of the split contact stress of the flange of the nuclear turbine cylinder is unqualified and less than or equal to 1, which indicates that the operation optimization control improvement needs to be carried out on the flange size, the number of bolts, the bolt diameter, the bolt material, the bolt pretightening force and the like in the design stage, and S1101 to S1106 are executed again until R_σcsUntil > 1.25.

For example, the operation optimization control is carried out on the flange bisection surface contact stress of the 1200MW nuclear power turbine cylinder by a flange bisection surface tightness design monitoring method under the action of bearing force load, thermal load and bolt pretightening force load of the nuclear power turbine cylinder.

In view of R_σcsWhen 2.285 is larger than 1.25, the design and monitoring of the flange median plane contact stress of the 1200MW nuclear turbine cylinder are qualified, which indicates that the flange median plane contact stress of the nuclear turbine cylinder is in a controlled state, and the design and monitoring of the flange median plane contact stress of the 1200MW nuclear turbine cylinder are finished.

In the embodiment of the disclosure, the ratio of the penetration gap of the split opening in the flange of the cylinder and the ratio of the contact stress meet the monitoring qualified conditions, which indicates that the split opening and the contact stress in the flange of the nuclear turbine cylinder are in a controlled state, and the safe operation of the nuclear turbine is ensured.

In practical application scenarios, when the valve casing and the cylinder of the nuclear turbine bear pressure and thermal load, the safety of the steady state and the transient state of the nuclear turbine may be affected. The safety design monitoring can be performed on the steady-state and transient-state strength of the pressure and thermal load bearing effect of the valve casing and the cylinder of the nuclear turbine, and can be understood by combining fig. 12, where fig. 12 is a schematic flow chart of a safety monitoring method of a nuclear turbine by a combined monitoring platform of a nuclear turbine according to another embodiment of the present disclosure, and as shown in fig. 12, the method includes:

and S1201, calculating the steady-state and transient strength safety design quantities of the valve casing and the cylinder of the nuclear turbine.

Inputting design parameters of a valve shell and a cylinder of the nuclear turbine, a three-dimensional mechanical model, a start-stop curve, pressure loads and heat loads of the valve shell and the cylinder, and material performance data by adopting a component model database, a load database and a material database, determining a weak part with maximum transient stress by using a method and a subprogram for designing and monitoring steady-state and transient-state strength of the action of bearing the pressure loads and the heat loads of the valve shell and the cylinder, and calculating surface equivalent stress (von-Misses stress) sigma of the weak part with the maximum transient stress of the valve shell and the cylinder under a steady-state rated working condition_e2And operating temperature t₂And surface equivalent stress (von mises stress) σ in transient operating conditions_e3And operating temperature t₃。

For example, based on a component model database, a load database and a material database, design parameters, a three-dimensional mechanical model, a start-stop curve, pressure loads and thermal loads of a valve shell and a cylinder of the 1200MW nuclear turbine and material performance data are input, a method and a subprogram for designing and monitoring steady-state and transient-state strength of the valve shell and the cylinder under the action of the pressure loads and the thermal loads are used, the weak part with the maximum transient stress is determined to be a root groove of a stator blade on the steam inlet side of the inner surface of an inner cylinder with the larger transient stress of the 1200MW nuclear turbine, a root groove of a stator blade on the steam inlet side of the inner surface of a high-pressure inner cylinder, and the surface equivalent stress sigma of the weak part with the weak strength under the steady-state rated working condition is determined_e258MPa and operating temperature t₂＝278DEG C and surface equivalent stress sigma under transient conditions_e3131MPa and operating temperature t₃＝194℃。

S1202, calculating the surface equivalent stress ratio of the nuclear turbine valve casing to the cylinder under the steady rated working condition.

Surface equivalent stress ratio R of nuclear turbine valve casing and cylinder under steady rated working condition_σe2cCalculated according to the following formula:

wherein σ_e2The surface equivalent stress of the weak strength part of the nuclear turbine valve casing and the cylinder under the steady rated working condition,

at an operating temperature t₂The 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 under the steady rated working condition_σe2cCalculated according to the following formula:

in the above-mentioned formula, the compound of formula,

at an operating temperature t₂Yield limit of the material at 278 ℃.

S1203, calculating the surface equivalent stress ratio of the nuclear turbine valve casing to the transient working condition of the cylinder.

Equivalent stress ratio R of valve shell of nuclear turbine and surface of cylinder under transient working condition_σe3cCalculated according to the following formula:

wherein σ_e3The surface equivalent stress of the valve shell of the nuclear turbine and the weak part of the cylinder under the transient working condition,

at an operating temperature t₃The yield limit of the lower material.

For example, the equivalent stress ratio R of the weak strength part of the valve casing and the cylinder of the 1200MW nuclear turbine on the surface under the transient working condition_σe3cCalculated according to the following formula:

in the above-mentioned formula, the compound of formula,

at an operating temperature t₃Yield limit of material 214MPa at 194 ℃.

And S1204, optimally controlling the operation of the valve casing and the cylinder of the nuclear turbine under the steady-state rated working condition strength.

The design and monitoring method for the steady state and transient state strength of the effect of bearing centrifugal force load and thermal load by the valve casing and the cylinder of the nuclear turbine carries out operation optimization control on the valve casing and the steady state rated working condition strength of the cylinder of the nuclear turbine:

(1) if R is_σe2cAnd (3) less than 1, the design and monitoring of the valve casing and the cylinder of the nuclear turbine are qualified under the steady-state rated working condition strength, which indicates that the valve casing and the cylinder of the nuclear turbine are in a controlled state under the steady-state rated working condition strength, and the design and monitoring of the valve casing and the cylinder under the steady-state rated working condition strength are finished.

(2) If R is_σe2cNot less than 1, the design and monitoring of the nuclear turbine valve casing and the cylinder are unqualified in the steady-state rated working condition strength, which indicates that the operation optimization control improvement on the structure size, the structure fillet, the supporting structure, the material model selection and the like is needed in the design stage, and S1201 to S1204 are executed again until R_σe2cUntil less than 1;

for example, the design monitoring method of the steady-state and transient-state strength of the valve casing and the cylinder of the nuclear turbine bearing the centrifugal load and the thermal load is used for carrying out operation optimization control on the valve casing and the cylinder steady-state rated working condition strength of the 1200MW nuclear turbine.

Due to R_σe2cAnd (3) when the pressure difference between the valve casing and the cylinder of the 1200MW nuclear turbine is less than 0.275 and less than 1, the design and monitoring of the valve casing and the cylinder of the 1200MW nuclear turbine are qualified in the steady-state rated working condition strength, which indicates that the valve casing and the cylinder of the nuclear turbine are in a controlled state in the steady-state rated working condition strength, and the design and monitoring of the valve casing and the cylinder of the 1200MW nuclear turbine are finished in the steady-state rated working condition strength.

And S1205, optimally controlling the operation of the valve shell and the cylinder of the nuclear turbine under the transient working condition strength.

Through the design monitoring method of the steady state and the transient state strength of the pressure load and the heat load of the valve shell and the cylinder of the nuclear turbine, the operation optimization control is carried out on the valve shell and the transient state working condition structural strength of the cylinder of the nuclear turbine:

(1) if R is_σe3cIf the structural strength of the valve casing and the cylinder of the nuclear turbine is less than 1, the structural strength design monitoring is qualified under the transient working condition, which indicates that the structural strength of the valve casing and the cylinder of the nuclear turbine is in a controlled state under the transient working condition, and the design monitoring of the structural strength of the valve casing and the cylinder of the nuclear turbine under the transient working condition is finished;

(2) if R is_σe3cNot less than 1, the structural strength design monitoring of the nuclear turbine valve casing and the cylinder under the transient working condition is unqualified, the operation optimization control improvement on the structure size, the structure fillet, the supporting structure, the material model selection and the like is indicated in the design stage, and S1201 to S1205 are executed until R_σe3cUntil less than 1.

For example, the design monitoring method of the steady-state and transient-state strength of the pressure load and heat load borne by the valve casing and the cylinder of the nuclear turbine is used for carrying out operation optimization control on the valve casing and the transient-state working condition structural strength of the cylinder of the 1200MW nuclear turbine.

Due to R_σe3cThe structural strength of the valve casing and the cylinder of the 1200MW nuclear turbine is designed and monitored to be qualified under the transient working condition, namely 0.408 is less than 1, which indicates that the valve casing and the cylinder of the nuclear turbine are in the transient working conditionThe structural strength of the transient working condition is in a controlled state, and the design and monitoring of the valve shell and the cylinder of the 1200MW nuclear turbine in the transient working condition are finished.

In the embodiment of the disclosure, the ratio of the equivalent stress of the surfaces of the valve casing and the cylinder under the steady-state rated working condition and the transient working condition meets the monitoring qualified condition, which indicates that the strength of the valve casing and the cylinder under the steady-state rated working condition and the structural strength under the transient working condition are in a controlled state, thereby ensuring the safe operation of the nuclear turbine.

The combined monitoring platform of a nuclear power turbine provided by the present disclosure can implement reliability monitoring of the nuclear power turbine, which can be further understood with reference to fig. 13, where fig. 13 is a schematic flow diagram of a monitoring method of a combined monitoring platform of a nuclear power turbine according to another embodiment of the present disclosure, and as shown in fig. 13, the method includes:

and 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 for the nuclear turbine, and the combined monitoring platform of the nuclear turbine can perform reliability monitoring on the nuclear turbine according to the received reliability monitoring instruction.

Furthermore, the reliability monitoring instruction can be received through a data processing server in the combined monitoring platform of the nuclear turbine, and the 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 operation state, the load born by the nuclear turbine 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 operation state data, load data and material performance data.

The data processing server can acquire running state data and load data matched with the reliability monitoring instruction and material performance data from a database connected with the data processing server.

S1302, based on the running state data and the load data matched with the reliability monitoring instruction and the material performance data, obtaining at least one of the following data:

acquiring monitoring data of dynamic strength and vibration reliability of a moving blade of a nuclear turbine under the action of centrifugal force, low-frequency exciting force and high-frequency exciting force;

acquiring torsional vibration reliability monitoring data of a multi-rotor system of a nuclear turbine subjected to power grid electrical disturbance fault;

acquiring first shaft system vibration reliability monitoring data of a rotor and a bearing system of a nuclear turbine under the action of forced vibration and self-excited vibration;

acquiring second shaft system vibration reliability monitoring data of a rotor and a bearing system of the nuclear turbine under the action of forced vibration and self-excited vibration;

and determining the dynamic strength and vibration monitoring data, the torsional vibration monitoring data, the first shaft system vibration reliability monitoring data and the second shaft system vibration reliability monitoring data as the reliability monitoring data of the nuclear turbine.

In the operation process of the nuclear turbine, partial components exist, and relevant attribute parameters such as the operation state, the load bearing effect, the material performance and the like of the components are greatly related to the reliable operation of the nuclear turbine.

Therefore, the data processing server can acquire at least one of the operation state data, the load data and the material performance data matched with the reliability monitoring instruction as corresponding reliability monitoring data based on the reliability monitoring instruction.

Optionally, the dynamic strength and vibration reliability monitoring data of the moving blade of the nuclear turbine under the action of the centrifugal force, the low-frequency exciting force and the high-frequency exciting force are obtained.

In the operation process of the nuclear turbine, the moving blade of the nuclear turbine has the possibility of generating vibration, wherein the related state of the moving blade of the nuclear turbine when bearing the centrifugal force, the low-frequency exciting force and the high-frequency exciting force has certain influence on the operation reliability of the nuclear turbine.

Further, relevant data when the moving blade of the nuclear turbine is subjected to the centrifugal force, the low-frequency exciting force and the high-frequency exciting force can be used as corresponding monitoring data, wherein the relevant data can comprise the dynamic strength relevant data and the vibration relevant data, and the dynamic strength relevant data and the vibration reliability relevant data are determined as the dynamic strength and vibration reliability monitoring data matched with the reliability monitoring instruction.

Optionally, torsional vibration reliability monitoring data of the multi-rotor system of the nuclear turbine subjected to 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 torsional vibration bearing disturbance faults of power grid electrical appliances, and has certain influence on the operation reliability of the nuclear turbine.

Furthermore, the torsional vibration safety of the multi-rotor system of the nuclear turbine, which is subjected to the power grid electrical disturbance fault, can be designed and monitored, and the corresponding torsional vibration data are used as the torsional vibration reliability monitoring data of the multi-rotor system, which is subjected to the power grid electrical disturbance fault.

Optionally, the vibration reliability monitoring data of the first shaft system of the nuclear turbine, which is subjected to the actions of forced vibration and self-excited vibration, of the rotor and bearing system, is obtained.

In the operation process of the nuclear turbine, shafting vibration may exist when a rotor and a bearing system of the nuclear turbine bear the action of forced vibration and self-excited vibration. The shafting vibration generated by the rotor and the bearing system has certain influence on the operation reliability of the nuclear power turbine.

Furthermore, the reliability monitoring of the rotor and the bearing system of the nuclear turbine can be realized through the relevant operation data of the rotor and the bearing system when the rotor and the bearing system bear the forced vibration and the self-excited vibration to generate shafting vibration.

In the embodiment of the disclosure, the operation state data of the rotor and the bearing system when bearing the forced vibration and the self-excitation action may be obtained, and the operation state data is determined as the corresponding first shaft system vibration reliability monitoring data, where the first shaft system vibration reliability monitoring data may include a critical rotation speed ratio of the rotor and the bearing system, and may further include an unstable rotation speed ratio of the rotor and the bearing system, and the like.

Optionally, second-shaft system vibration reliability monitoring data of the rotor and bearing system of the nuclear turbine subjected to the effects of forced vibration and self-excited vibration are obtained.

In the embodiment of the disclosure, shafting vibration generated when a rotor and a bearing system of the nuclear turbine bear the actions of forced vibration and self-excited vibration can be monitored, and reliability monitoring of the nuclear turbine is realized based on a monitoring result corresponding to the shafting vibration.

Furthermore, the monitoring data of the shafting vibration of the rotor and the bearing system of the nuclear turbine under the action of forced vibration and self-excited vibration can be obtained, and the monitoring data is determined as the corresponding second shafting vibration reliability monitoring data. The second shaft system vibration reliability monitoring data can comprise a ratio of the shaft neck on-line monitoring shaft vibration relative displacement, a ratio of the bearing seat on-line monitoring vibration speed and the like.

Optionally, the dynamic strength and vibration reliability monitoring data, the torsional vibration reliability monitoring data, the first shaft system vibration reliability monitoring data and the second shaft system vibration reliability monitoring data are determined as the reliability monitoring data of the nuclear turbine.

In the embodiment of the disclosure, monitoring coverage of components having influence on the operational reliability of the nuclear turbine can be realized through the dynamic strength and vibration reliability monitoring data, the torsional vibration reliability monitoring data, the first shaft system vibration reliability monitoring data and the second shaft system vibration reliability monitoring data.

Therefore, the dynamic strength and vibration reliability monitoring data, the torsional vibration reliability monitoring data, the first shaft system vibration reliability monitoring data and the second shaft system vibration reliability monitoring data can be determined as the reliability monitoring data of the nuclear turbine.

According to the combined monitoring platform of the nuclear turbine, reliability monitoring is carried out on the nuclear turbine according to the obtained monitoring data, at least one of dynamic strength and vibration reliability monitoring data, torsional vibration reliability monitoring data, first shaft system vibration reliability monitoring data and second shaft system vibration reliability monitoring data which correspond to the nuclear turbine is obtained from a corresponding database, and then the reliability monitoring data of the nuclear turbine matched with the reliability monitoring instruction are determined. According to the method and the device, the reliability monitoring of the steam turbine is realized through the reliability monitoring data, the reliability monitoring effect of the nuclear steam turbine is optimized, and the high-reliability monitoring of the nuclear steam turbine is realized.

In order to better understand the embodiments, 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 may be further combined with the following embodiments.

In an actual application scenario, reliability design and monitoring can be performed on the dynamic strength and the vibration safety of the nuclear turbine moving blade subjected to the centrifugal force, the low-frequency excitation force and the high-frequency excitation force, which can be understood by referring to fig. 14, where fig. 14 is a schematic flow chart of a method for monitoring the reliability of a nuclear turbine by using a nuclear turbine combined monitoring platform according to an embodiment of the present disclosure, and as shown in fig. 14, the method includes:

s1401, calculating the operation 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, inputting design parameters, a three-dimensional mechanical model, a centrifugal force load, an exciting force load and material mechanical property data of a moving blade of the nuclear turbine, designing and monitoring a dynamic strength and vibration of the moving blade under the action of centrifugal force, low-frequency exciting force and high-frequency exciting force, and calculating the vibration stress sigma of the moving blade of the nuclear turbine_vVibration resistance σ_aAllowable safety factor of dynamic strength_f]First order vibration frequency f₁At the maximum working speed limit (1+0.01) n₀Frequency f of vibration of_d1N is the lowest working rotating speed (1-0.03)₀Time-limited vibration frequency f_d2M-order diameter vibration frequency f of long blades connected in full circle_dmAnd the working speed n of the nuclear turbine₀。

For example, inBased on a component model database, a load database and a material database of the nuclear power turbine, inputting design parameters, a three-dimensional mechanical model, a centrifugal force load, an excitation force load and material mechanical property data of a moving blade of the 1200MW nuclear power turbine, and calculating the running state data of the moving blade at a certain stage of the 1200MW nuclear power turbine by using a method and a subprogram for designing and monitoring the dynamic strength and the vibration of the moving blade under the action of the centrifugal force, the low-frequency excitation force and the high-frequency excitation force_v18.83MPa, vibration resistance intensity sigma_a253.99MPa, allowable safety factor of dynamic strength [ S [ ]_f]2.45, first order vibration frequency f₁123Hz, at the highest limit of the operating speed (1+0.01) n₀Frequency f of vibration of_d1128Hz, lowest (1-0.03) n at operating speed₀Time-limited vibration frequency f_d2107Hz, and m of the whole connected long blade is 6-step diameter vibration frequency f_dm1186Hz and operating speed n of a nuclear turbine₀＝1500r/min＝25Hz。

S1402, calculating the dynamic strength safety ratio of the moving blade.

Safe ratio R of dynamic strength of moving blade of nuclear turbine subjected to centrifugal force and steam flow exciting force_σvCalculated according to the following formula:

in the above formula, σ_aThe vibration resistance of the rotor blade, σ_vIs the vibration stress of the moving blade, [ S ]_f]Safety factors are allowed for the dynamic strength of the moving blades.

For example, the moving blade of the 1200MW nuclear turbine bears the safe ratio R of the dynamic strength of the centrifugal force and the steam flow exciting force_σvCalculated according to the following formula:

in the above formula, σ_aThe vibration resistance strength of the moving blade is 253.99MPa, sigma_vThe vibration stress of the rotor blade is 18.83MPa, [ S ]_f]The safety factor of 2.45 is allowed for the dynamic strength of the moving blade.

And S1403, calculating a first frequency resonance ratio of the moving blade avoiding 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 avoiding the low frequency excitation force frequency.

First-order vibration frequency avoidance low-frequency exciting force frequency lower limit ratio R of nuclear turbine moving blade_d1And an upper ratio R_u1Respectively according to the following formula:

in the above formula, f_d1For the moving blade at the maximum working speed limit (1+0.01) n₀Frequency of vibration of time, f_d2For the moving blade at the lowest working rotating speed (1-0.03) n₀The vibration frequency of the time, K is the rotating speed multiplying power of the exciting force, n₀The working rotating speed of the nuclear turbine.

For example, the first-order vibration frequency of the moving blade of the 1200MW nuclear turbine avoids the lower limit ratio R of the low-frequency excitation force frequency_d1And an upper ratio R_u1Respectively according to the following formula:

in the above formula, f_d1To moveThe vibration frequency of the blade at the maximum working rotation speed limit (1+0.01) n0 is 128Hz, f_d2For the moving blade at the lowest working rotating speed (1-0.03) n₀The vibration frequency is 107Hz, K is 5, the rotating speed multiplying power of the exciting force, and n₀The working speed 1500r/min of the 1200MW nuclear power turbine is 25 Hz.

And S1404, calculating a second frequency resonance ratio of the moving blade avoiding the high-frequency excitation force.

First-order vibration frequency of moving blade of nuclear turbine avoids high-frequency exciting force frequency Z_nn₀Ratio of resonance Δ f_hCalculated according to the following formula:

in the above formula, f₁Is the first order vibration frequency, Z, of the moving blade_nNumber of stationary blades, n₀The working rotating speed of the nuclear turbine.

For example, the first-order vibration frequency of the moving blade of the 1200MW nuclear turbine avoids the second frequency resonance ratio delta f of the high-frequency exciting force_hCalculated according to the following formula:

in the above formula, f₁Is the first order vibration frequency of the moving blade of 123Hz, Z_nNumber of stationary blades 60, n₀The working speed of the nuclear turbine is 1500 r/min-25 Hz.

S1405, calculating a third frequency resonance ratio of m-order diameter vibration frequency of the whole circle of connected long blades to avoid the high-frequency exciting force.

M-order diameter vibration frequency of full circle connected long blade avoids high frequency exciting force frequency Z_nn₀Ratio of resonance Δ f_mCalculated according to the following formula:

in the above formula, f_dmThe m-order diameter vibration frequency of the long blades is connected for a whole circle, m is the pitch diameter number of the vibration of the whole circle of blades, Z_nThe number of stationary blades.

For example, the m-step diameter vibration frequency of the whole circle connected long blade avoids the third frequency resonance ratio delta f of the high-frequency exciting force_mCalculated according to the following formula:

in the above formula, f_dmThe m-6 step diameter vibration frequency 1186Hz of the whole circle connected long blade, the m-6 step diameter number of the whole circle blade vibration, and Z_nThe number of stationary blades is 60.

And S1406, optimizing and controlling the operation of the safety of the dynamic strength of the moving blade.

The method for monitoring the dynamic strength and vibration of the moving blade of the nuclear turbine under the action of centrifugal force, low-frequency exciting force and high-frequency exciting force comprises the following steps of (1) carrying out operation optimization control on the safety of the dynamic strength of the moving blade of the nuclear turbine:

(1) if R is_σvAnd if the safety is higher than 1, the design and monitoring of the dynamic strength safety of the moving blade of the nuclear turbine are qualified, which indicates that the dynamic strength safety of the moving blade of the nuclear turbine is in a controlled state, and the design and monitoring of the vibration strength safety of the moving blade are finished.

(2) If R is_σvLess than or equal to 1, the safety design and monitoring of the dynamic strength of the moving blade of the nuclear turbine are unqualified, the requirement of carrying out operation optimization control improvement on the width and thickness of the blade profile of the moving blade, the structure fillet, the connecting structure, the shroud thickness, the material mark and the like in the design stage is shown, and S1401 to S1406 are executed again until R_σvUntil > 1.

For example, through a dynamic strength optimization improvement strategy, the operation optimization control is carried out on the dynamic strength safety of the moving blade of the 1200MW nuclear turbine:

(1) if R is_σvThe safety of the dynamic strength of the moving blade of the 1200MW nuclear turbine is qualified by design and monitoring, wherein 5.51 is more than 1The method shows that the dynamic strength safety of the moving blade of the 1200MW nuclear turbine is in a controlled state, and the design and monitoring of the vibration strength safety of the moving blade are finished.

S1407, the moving blade avoids the operation optimization control of the low-frequency excitation force frequency resonance.

The method for monitoring the dynamic strength and vibration of the moving blade of the nuclear turbine under the action of centrifugal force, low-frequency exciting force and high-frequency exciting force comprises the following steps of (1) avoiding low-frequency exciting force frequency resonance to carry out operation optimization control on the moving blade of the nuclear turbine:

(1) if R is_d1> 5% and R_u1And if the frequency of the low-frequency excitation force frequency resonance is avoided by the moving blade, the design and monitoring are qualified, which shows that the moving blade of the nuclear turbine is in a controlled state and the design and monitoring of the moving blade avoiding the frequency of the low-frequency excitation force frequency resonance is finished.

(2) If R is_d1Less than or equal to 5% or R_u1Less than or equal to 3 percent, unqualified design and monitoring of nuclear turbine moving blade avoiding low-frequency excitation force frequency resonance, showing that the operation optimization control improvement needs to be carried out on the blade profile width and thickness, the structure fillet, the connecting structure, the shroud thickness, the material mark and the like of the moving blade in the design stage, and executing S1401 to S1407 again until R_d1> 5% and R_u1Until > 3%.

For example, through an optimization and improvement strategy that the moving blade avoids low-frequency excitation force frequency resonance, the moving blade of the 1200MW nuclear turbine avoids the low-frequency excitation force frequency resonance to carry out operation optimization control:

(1) if R is_d13.60% > 5% and R_u11.90% > 3%, this model 1200MW nuclear power turbine moving blade avoids low frequency exciting force frequency resonance design control to be qualified, shows that this model 1200MW nuclear power turbine moving blade avoids low frequency exciting force frequency resonance and is in controlled state, and the moving blade avoids the design control of low frequency exciting force frequency resonance to finish.

And S1408, the moving blade avoids the operation optimization control of the high-frequency excitation force frequency resonance.

The method for monitoring the dynamic strength and vibration of the moving blade of the nuclear turbine under the action of centrifugal force, low-frequency exciting force and high-frequency exciting force comprises the following steps of (1) avoiding high-frequency exciting force frequency resonance to carry out operation optimization control on the moving blade of the nuclear turbine:

(1) if Δ f_hAnd the design and monitoring of the moving blade of the nuclear turbine avoiding the high-frequency exciting force frequency resonance is qualified, which indicates that the moving blade is in a controlled state avoiding the high-frequency exciting force frequency resonance, and the design and monitoring of the moving blade avoiding the high-frequency exciting force frequency resonance are finished.

(2) If Δ f_hLess than 5 percent, the nuclear turbine moving blade avoids the high-frequency excitation force frequency resonance design and is unqualified to monitor, which shows that the operation optimization control improvement needs to be carried out on the blade profile width, the thickness, the structure fillet, the connecting structure, the shroud thickness and the material mark of the moving blade in the design stage, and S1401 to S1408 are executed again until delta f_hNot less than 5%.

For example, through an optimization and improvement strategy that the moving blade avoids high-frequency excitation force frequency resonance, the moving blade of the 1200MW nuclear turbine avoids the high-frequency excitation force frequency resonance to carry out operation optimization control:

(1) if Δ f_h91.80% or more than 5%, the design and monitoring of the moving blade of the 1200MW nuclear power turbine for avoiding the high-frequency excitation force frequency resonance is qualified, the moving blade is in a controlled state for avoiding the high-frequency excitation force frequency resonance, and the design and monitoring of the moving blade for avoiding the high-frequency excitation force frequency resonance are finished.

And S1409, performing operation optimization control on the whole circle of connected long blades to avoid the frequency resonance of the high-frequency exciting force.

The method for monitoring the dynamic strength and vibration of the moving blade of the nuclear turbine under the action of centrifugal force, low-frequency exciting force and high-frequency exciting force comprises the following steps of (1) carrying out operation optimization control on the whole circle of the long blade connected with the nuclear turbine by avoiding high-frequency exciting force frequency resonance:

(1) if Δ f_mAnd the design and monitoring that the whole-circle connected long blade avoids the high-frequency exciting force frequency resonance is qualified, which indicates that the whole-circle connected long blade avoids the high-frequency exciting force frequency resonance and is in a controlled state, and the design and monitoring that the whole-circle connected long blade avoids the high-frequency exciting force frequency resonance is finished.

(2) If Δ f_mLess than 5 percent, the whole circle of the long blade connected with the air nuclear power turbine avoids the high-frequency excitation force frequency resonance design and monitoring to be unqualified, which shows that the operation optimization control improvement needs to be carried out on the blade profile width and thickness, the structure fillet, the connecting structure, the shroud thickness, the material grade and the like of the final-stage moving blade in the design stage, and S1401 to S1409 are executed again until delta f_mNot less than 5%.

For example, through an optimization and improvement strategy that the long blades are connected in a full circle to avoid high-frequency excitation force frequency resonance, the operation optimization control is carried out on the long blades connected in the full circle to avoid the high-frequency excitation force frequency resonance of the 1200MW nuclear turbine:

(1) if Δ f_mThe design and monitoring that the whole circle of the long blade avoids the high-frequency exciting force frequency resonance is qualified, the whole circle of the long blade is indicated to be in a controlled state when the whole circle of the long blade avoids the high-frequency exciting force frequency resonance, and the design and monitoring that the whole circle of the long blade avoids the high-frequency exciting force frequency resonance is finished.

In the embodiment of the disclosure, the dynamic strength and the vibration safety of the moving blade 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 an actual application scenario, reliability design monitoring can be performed on torsional vibration safety of a multi-rotor system of a nuclear turbine, which is subjected to a power grid electrical disturbance fault, as can be understood by referring to fig. 15, fig. 15 is a schematic flow diagram of a method for monitoring reliability of a nuclear turbine by using a combined monitoring platform of a nuclear turbine according to another embodiment of the present disclosure, as shown in fig. 15, the method includes:

s1501, calculating the torsional vibration design quantity of the multi-rotor system subjected to the electrical disturbance fault of the power grid.

Inputting design parameters, three-dimensional mechanical models and material mechanical property data of a multi-rotor system of the nuclear turbine based on a component model database, a load database and a material database of the nuclear turbine, and using the multi-rotor system to bear torsional vibration design monitoring of electrical disturbance faults of a power gridCalculating the torsional vibration frequency F closest to 45Hz of the multi-rotor system of the nuclear turbine by using the method and the subprogram₁Torsional vibration frequency F closest to the torsional vibration frequency of 55Hz₂And a torsional vibration frequency F closest to 93Hz₃A torsional vibration frequency F closest to 108Hz₄And the maximum shear stress sigma of the multi-rotor system of the nuclear turbine in the two-phase short circuit_τmax。

For example, based on a component model database, a load database and a material database of the 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, a torsional vibration design monitoring method and a subprogram of the multi-rotor system bearing power grid electrical disturbance fault are used, and a torsional vibration frequency F closest to 45Hz of the multi-rotor system of the 1200MW nuclear turbine is calculated₁Torsional vibration frequency F of 15.58Hz and nearest 55Hz₂Torsional vibration frequency F of 15.58Hz and nearest 93Hz₃Torsional vibration frequency F closest to 108Hz at 90.51Hz₄Maximum shear stress sigma of multi-rotor system of nuclear turbine in two-phase short circuit at 172.14Hz_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 nuclear power turbine multi-rotor system torsional vibration frequency avoiding power grid working frequency_L1And an upper ratio R_H1Respectively according to the following formula:

in the above formula, F₁Is the torsional vibration frequency F closest to 45Hz₂The torsional vibration frequency which is closest to the torsional vibration frequency of 55 Hz.

For example, the model 1200MWLower limit ratio R of nuclear power turbine multi-rotor system torsional vibration frequency avoiding power grid working frequency_L1And an upper ratio R_H1Respectively according to the following formula:

in the above formula, F₁The torsional vibration frequency is 15.58Hz, F which is closest to 45Hz₂The torsional vibration frequency, which is the closest torsional vibration frequency to 55Hz, is 87.61 Hz.

And S1503, calculating the ratio of the torsional vibration frequency of the multi-rotor system to the doubled working frequency of the power grid.

Lower limit ratio R of nuclear power turbine multi-rotor system torsional vibration frequency avoiding electric network double working frequency_L2And an upper ratio R_H2Respectively according to the following formula:

in the above formula, F₃Is the torsional vibration frequency F closest to 93Hz₄The torsional vibration frequency closest to 108 Hz.

For example, the torsional vibration frequency of the multi-rotor system of the 1200MW nuclear steam turbine avoids the lower limit ratio R of twice the working frequency of the power grid_L2And an upper ratio R_H2Respectively according to the following formula:

in the above formula, F₃The torsional vibration frequency is 90.51Hz, F closest to 93Hz₄The torsional vibration frequency of 172.14Hz was closest to 108 Hz.

S1504, calculating the torsional vibration stress ratio of the multi-rotor system when the two phases are short-circuited.

Torsional vibration stress ratio R of nuclear turbine multi-rotor system when two-phase short circuit occurs in electric power system_στCalculated according to the following formula:

in the above formula, σ_τmaxThe maximum shearing stress of the multi-rotor system when two phases of the power grid are short-circuited,

is the yield limit of the material at the operating temperature.

For example, the torsional vibration stress ratio R of the multi-rotor system of the nuclear turbine when the two-phase short circuit occurs in the power system_στCalculated according to the following formula:

in the above formula, σ_τmaxThe maximum shearing stress of the multi-rotor system is 275.83MPa when two phases of the power grid are short-circuited,

is the yield limit of 630MPa of the material at the working temperature.

And S1505, optimally controlling the operation of the torsional vibration frequency of the multi-rotor system to avoid the working frequency of the power grid.

By the torsional vibration design monitoring method for the multi-rotor system of the nuclear turbine to bear the electrical disturbance fault of the power grid, the torsional vibration frequency of the multi-rotor system of the nuclear turbine avoids the working frequency of the power grid to carry out operation optimization control:

(1) if R is_L1< 1 and R_H1And if the frequency is higher than 1, the design monitoring of avoiding the working frequency of the power grid by the torsional vibration frequency of the multi-rotor system of the nuclear turbine is qualified, which indicates that the frequency avoiding the working frequency of the power grid by the torsional vibration frequency of the multi-rotor system is in a controlled state, and the design monitoring of avoiding the working frequency of the power grid by the torsional vibration frequency of the multi-rotor system is finished.

(2) If R is_L1Not less than 1 or R_H1Less than or equal to 1, the design monitoring that the torsional vibration frequency of the nuclear power turbine multi-rotor system avoids the power grid working frequency is unqualified, which indicates that the operation optimization control improvement needs to be carried out on the structure of the rotor or the coupling in the design stage, the material with better yield strength is used instead, or the structure geometric dimension of the multi-rotor system is optimized, and S1501 to S1505 are executed again until R is up to_L1< 1 and R_H1Until > 1.

For example, by a torsional vibration design monitoring method for a multi-rotor system of a nuclear turbine to bear the electrical disturbance fault of a power grid, the torsional vibration frequency of the multi-rotor system of the 1200MW nuclear turbine avoids the working frequency of the power grid to carry out operation optimization control:

(1) if R is_L10.35 < 1 and R_H1When the torsional vibration frequency of the multi-rotor system of the 1200MW nuclear power turbine is 1.59 & gt 1, the design monitoring for avoiding the working frequency of the power grid is qualified, the condition that the torsional vibration frequency of the multi-rotor system is in a controlled state avoiding the working frequency of the power grid is shown, and the design monitoring for avoiding the working frequency of the power grid by the torsional vibration frequency of the multi-rotor system is finished.

And S1506, the multi-rotor system torsional vibration frequency avoids the operation optimization control of twice working frequency of the power grid.

By the torsional vibration design monitoring method for the multi-rotor system of the nuclear turbine to bear the electrical disturbance fault of the power grid, the torsional vibration frequency of the multi-rotor system of the nuclear turbine avoids twice the working frequency of the power grid to carry out operation optimization control:

(1) if R is_L2< 1 and R_H2The 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, which indicates that the torsional vibration frequency of the multi-rotor system avoids the second power gridThe multiple working frequency is in a controlled state, and the design monitoring of the multi-rotor system torsional vibration frequency avoiding the power grid twice working frequency is finished.

(2) If R is_L2Not less than 1 or R_H2Less than or equal to 1, the design monitoring that the torsional vibration frequency of the nuclear power turbine multi-rotor system avoids the double working frequency of the power grid is unqualified, which shows that the operation optimization control improvement of the structure of the rotor or the coupling is needed in the design stage, the material with better yield strength is used instead, or the structure geometric dimension of the multi-rotor system is optimized, and S1501 to S1506 are executed again until R is up to_L2< 1 and R_H2Until > 1.

For example, by a torsional vibration design monitoring method for a multi-rotor system of a nuclear turbine to bear the electrical disturbance fault of a power grid, the torsional vibration frequency of the multi-rotor system of the 1200MW nuclear turbine avoids twice the working frequency of the power grid to carry out operation optimization control:

(1) if R is_L20.97 < 1 and R_H2When the torsional vibration frequency of the multi-rotor system of the 1200MW nuclear power turbine is 1.59 & gt 1, the design monitoring for avoiding the twice working frequency of the power grid by the torsional vibration frequency is qualified, which indicates that the twice working frequency of the multi-rotor system avoiding the power grid by the torsional vibration frequency is in a controlled state, and the design monitoring for avoiding the twice working frequency of the power grid by the torsional vibration frequency of the multi-rotor system is finished.

And S1507, optimally controlling the operation of the torsional vibration stress of the multi-rotor system when two-phase short circuit occurs.

By the torsional vibration design monitoring method for the multi-rotor system of the nuclear turbine to bear the electrical disturbance fault of the power grid, the torsional vibration stress of the multi-rotor system of the nuclear turbine is operated and optimized when two-phase short circuit occurs:

(1) if R is_στIf the frequency is less than 1, the torsional vibration stress of the multi-rotor system of the nuclear turbine is qualified in design and monitoring when the two-phase short circuit occurs, the torsional vibration stress of the multi-rotor system is in a controlled state, and the design and monitoring of the torsional vibration stress of the multi-rotor system are finished.

(2) If R is_στNot less than 1, 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 operation optimization control needs to be carried out on the structure of the rotor or the coupling in the design stageImproving, changing to material with better yield strength, or optimizing the structural geometry of the multi-rotor system, and executing S1501 to S1507 again until R_στUntil less than 1.

For example, by a torsional vibration design monitoring method for a multi-rotor system of a nuclear turbine to bear the electrical disturbance fault of a power grid, the torsional vibration stress of the multi-rotor system of the 1200MW nuclear turbine is operated and optimized and controlled when a two-phase short circuit occurs:

(1) if R is_στAnd (3) when the two-phase short circuit occurs, the torsional vibration stress of the multi-rotor system of the 1200MW nuclear power turbine is qualified in design monitoring, which indicates that the torsional vibration stress of the multi-rotor system is in a controlled state, and the design monitoring of the torsional vibration stress 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 subjected to the electrical 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 an actual application scenario, reliability design monitoring can be performed on shafting vibration safe operation of a nuclear turbine rotor and a bearing system under the actions of forced vibration and self-excited vibration, which can be understood by referring to fig. 16, where fig. 16 is a schematic flow diagram of a method for monitoring reliability of a nuclear turbine by using a combined monitoring platform of a nuclear turbine according to another embodiment of the present disclosure, and as shown in fig. 16, the method includes:

s1601, inputting a shafting vibration online monitoring value of the rotor and bearing system under the action of forced vibration and self-excited vibration.

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 a rotor and bearing system bearing the action of forced vibration and self-excited vibration are input into a nuclear turbine rotor journal to monitor the peak value D of the shaft vibration relative displacement peak on line_p-pr(mum) on-line monitoring vibration speed V with bearing seat_b(mm/s), monitoring the safety of operation vibration.

For example, based on nuclear turbinesA component model database, a load database and a material database of the machine, a shafting vibration operation monitoring method and a subprogram for bearing the action of forced vibration and self-excited vibration of a rotor and a bearing system are input into a shaft neck on-line monitoring shaft vibration relative displacement peak-to-peak value D of a rotor shaft neck of a 1200MW nuclear steam turbine _p-pr100 mu m vibration speed V on-line monitored with bearing seat_bAnd 4mm/s, and monitoring the operation vibration safety.

And S1602, calculating the ratio of the shaft vibration relative displacement of the rotor journal on-line monitoring.

Online monitoring shaft vibration relative displacement ratio R of nuclear power steam turbine rotor shaft neck_p-prCalculated according to the following formula:

in the above formula, D_p-prAnd monitoring the peak value (mum) of the shaft vibration relative displacement peak on line for the shaft neck of the nuclear power turbine rotor.

For example, the shaft vibration relative displacement ratio R of a rotor journal of a 1200MW nuclear power turbine is monitored on line_p-prCalculated according to the following formula:

in the above formula, D_p-prThe peak value of the shaft vibration relative displacement peak is monitored by 100 microns on line for the shaft neck of the 1200MW nuclear power turbine rotor.

S1603, calculating the ratio of the online monitoring vibration speed of the bearing seat.

Online monitoring vibration speed V of bearing seat of nuclear turbine_bRatio R_bCalculated according to the following formula:

in the above formula, V_bMonitoring the vibration speed (mm/s) for the bearing seat on line, [ V ]_b]For bearingsThe seat monitors the alarm value (mm/s) of the vibration speed online.

For example, the bearing seat of the 1200MW nuclear power turbine is used for monitoring the vibration speed V on line_bRatio R_bCalculated according to the following formula:

in the above formula, V_bOn-line monitoring of the vibration speed, V, for the bearing blocks_b＝4mm/s，[V_b]Monitoring the alarm value (mm/s) of the vibration speed for the bearing block on line, for n₀1500r/min and 1800r/min half-speed nuclear turbine [ V ]_b]5.3mm/s for n₀3000r/min and 3600r/min full-speed nuclear turbine [ V ]_b]＝7.5mm/s。

And S1604, carrying out operation optimization control on the rotor journal on-line monitoring shaft vibration relative displacement.

By a shafting vibration operation monitoring method for bearing the effects of forced vibration and self-excited vibration on a nuclear turbine rotor and bearing system, the operation and maintenance optimization control is carried out on the nuclear turbine rotor shaft neck on-line monitoring shaft vibration relative displacement:

(1) if R is_p-prIf the shaft vibration relative displacement is less than 1, the operation monitoring of the shaft neck of the rotor of the nuclear power steam turbine for on-line monitoring of the shaft vibration relative displacement is qualified, and the fact that the shaft vibration relative displacement of the shaft neck of the rotor of the nuclear power steam turbine for on-line monitoring is in a controlled state is shown.

(2) If R is_p-prAnd (4) not less than 1, the nuclear power steam turbine rotor journal online monitoring of the relative displacement operation monitoring of the shaft vibration is unqualified, the condition that the steam turbine rotor and the bearing need to be overhauled in the use stage is indicated, the reason for the overlarge vibration of the rotor and the bearing is searched and improved, and S1601 to S1604 are executed again until R_p-prUntil less than 1.

For example, through a shafting vibration operation monitoring method for a nuclear turbine rotor and a bearing system bearing the action of forced vibration and self-excited vibration, operation and maintenance optimization control is performed on the journal of the 1200MW nuclear turbine rotor on-line monitoring shaft vibration relative displacement.

Due to R_p-prWhen the shaft vibration relative displacement is monitored on line, the shaft vibration relative displacement is monitored to be qualified, and the shaft vibration relative displacement is monitored on line by the shaft neck of the 1200MW nuclear steam turbine rotor shaft neck, so that the nuclear steam turbine rotor shaft neck is in a controlled state.

And S1605, the bearing seat monitors the vibration speed on line to optimize and control.

By a shafting vibration operation monitoring method for bearing the effects of forced vibration and self-excited vibration on a nuclear turbine rotor and bearing system, the operation and maintenance optimization control is carried out on the on-line monitoring vibration speed of a nuclear turbine bearing seat:

(1) if R is_p-pbAnd (3) less than 1, the operation monitoring of the on-line monitoring vibration speed of the bearing seat of the nuclear turbine is qualified, and the on-line monitoring tile vibration displacement of the bearing of the nuclear turbine is in a controlled state.

(2) If R is_bAnd (3) not less than 1, unqualified operation monitoring of the on-line monitoring vibration speed of the bearing seat of the nuclear turbine indicates that the rotor and the bearing of the turbine are required to be overhauled in the use stage, the reason for the overlarge vibration of the rotor and the bearing is searched and improved, and S1601 to S1605 are executed again until R_bUntil less than 1.

For example, through a shafting vibration operation monitoring method for a nuclear turbine rotor and bearing system bearing the action of forced vibration and self-excited vibration, operation and maintenance optimization control is carried out on the vibration speed of the 1200MW nuclear turbine bearing pedestal on-line monitoring.

(1) In view of R_bThe operation monitoring of the on-line monitoring vibration speed of the bearing seat of the 1200MW nuclear turbine is qualified, which indicates that the on-line monitoring vibration speed of the bearing seat of the nuclear turbine is in a controlled state, wherein the operation monitoring is 0.755 < 1.

In the embodiment of the disclosure, the safety of shafting vibration of a rotor and a bearing system of the nuclear turbine can be accurately monitored, 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 long-period safe operation of the nuclear turbine is ensured.

In the description herein, references to the description of the term "one embodiment," "some embodiments," "an example," "a specific example," or "some examples," etc., mean 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, the schematic representations of the terms used above are not necessarily intended to refer 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, various embodiments or examples and features of different embodiments or examples described in this specification can be combined and combined by one skilled in the art without contradiction.

Furthermore, the terms "first", "second" and "first" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include at least one such feature. In the description of the present disclosure, "a plurality" means at least two, e.g., two, three, etc., unless explicitly specifically limited 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 steps of a custom logic function or process, and alternate 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.

The logic and/or steps represented in the flowcharts or otherwise described herein, e.g., an ordered listing of executable instructions that can be considered to implement 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). Additionally, the computer-readable medium could even be paper or another suitable medium upon which the program is printed, as the program can 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 embodiments, the various steps or methods may be implemented in software or firmware stored in memory and executed by a suitable instruction execution system. If implemented in hardware, as in another embodiment, any one or combination of the following techniques, which are known in the art, may be used: a discrete logic circuit having a logic gate circuit for implementing a logic function on a data signal, an application specific integrated circuit having an appropriate combinational logic gate circuit, a Programmable Gate Array (PGA), a Field Programmable Gate Array (FPGA), or the like.

It will be understood by those skilled in the art that all or part of the steps carried by the method for implementing the above embodiments may be implemented by hardware related to instructions of a program, which may be stored in a computer readable storage medium, and when the program is executed, the program includes one or a combination of the steps of the method embodiments.

In addition, functional units in the embodiments of the present disclosure may be integrated into one processing module, or each unit may exist alone physically, or two or more units are integrated into one module. The integrated module can be realized in a hardware mode, and can also be realized in a software functional module mode. The integrated module, if implemented in the form of a software functional module and sold or used as a stand-alone product, may also be stored in a computer readable storage medium.

The storage medium mentioned above may be a read-only memory, a magnetic or optical disk, etc. Although embodiments of the present disclosure have been shown and described above, it is understood that the above embodiments are exemplary and should not be construed as limiting the present disclosure, and that changes, modifications, substitutions and alterations may be made to the above embodiments by those of ordinary skill in the art within the scope of the present disclosure.

It should be understood that various forms of the flows shown above may be used, with steps reordered, added, or deleted. For example, the steps described in the present disclosure may be executed in parallel or sequentially or in different orders, and are not limited herein as long as the desired results of the technical solutions disclosed in the present disclosure can be achieved.

The above detailed description should not be construed as limiting the scope of the disclosure. It should be understood by those skilled in the art that various modifications, combinations, sub-combinations and substitutions may be made in accordance with design requirements and other factors. Any modification, equivalent replacement, and improvement made within the spirit and principle of the present disclosure should be included in the scope of protection of the present disclosure.

Serial number

Index value

Number of cold-state annual starts y_cOnce/time

Number of annual mean temperature state starts y_wOnce/time

Number of annual average thermal state starts y_hOnce/time

Number of annual average normal stops y_nOnce/time

Number of annual average operating hours t_y/h

1. A combined monitoring platform of a nuclear turbine is characterized by 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 operation state data of the nuclear turbine under multiple 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 for the nuclear turbine, 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, calling the load database and the material database, acquiring running state data and load data matched with the monitoring instruction from the load database, and determining monitoring data corresponding to the monitoring instruction according to the matched running state data and load data and the material performance data, wherein the monitoring data comprises at least one of service life monitoring data, safety monitoring data and reliability monitoring data.

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 obtained, obtain the component design parameters 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 parameters, the three-dimensional mechanical model, the operating state data and the load data matched with the monitoring instruction, and the material performance data.

3. The monitoring platform of claim 1, wherein the load database stores at least one of:

pressure load, centrifugal force load, heat load and bolt pre-tightening force load of the nuclear turbine;

the rigidity coefficient and the damping coefficient of the bearing oil film;

measuring the metal temperature of a point at the depth of 85-95% of the wall thickness of the inner cylinder;

measuring the metal temperature at the position of 85-95% of the wall thickness of the valve shell and the cylinder and measuring the metal temperature at the position of 45-50% of the wall thickness of the valve shell and the cylinder;

the metal temperature of the outer side of the flange middle section is measured under the condition that steam leaks from the weakest part of the flange middle section of the cylinder;

the shaft vibration relative displacement peak value Dp-pr of the nuclear power steam turbine rotor shaft neck on-line monitoring and the vibration speed V of the bearing seat on-line monitoring_b；

The start-stop curve of the nuclear turbine.

4. The monitoring platform of claim 1, wherein the materials database stores at least one of:

the nuclear turbine has the advantages of material physical property, material mechanical property, high-temperature long-time mechanical property and fatigue fracture mechanical property.

5. The monitoring platform according to any one of claims 2 to 4, wherein the data processing server is further configured to generate an optimization and improvement strategy for the nuclear turbine according to the monitoring data, and perform operation optimization and control on the nuclear turbine according to the optimization and improvement strategy.

6. The monitoring platform of claim 5, further comprising: the webpage server is connected with the data processing server;

and 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.

7. The monitoring platform of claim 6, further comprising:

the client browser is connected with the webpage server;

and 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 and displaying the webpage data sent by the webpage server.

8. The monitoring platform of claim 6, 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-class web page data.

9. The monitoring platform of claim 6, 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.

10. The monitoring platform of claim 6, wherein the monitoring platform is a distributed network architecture comprising a dispatch server, a plurality of the data processing servers, and a plurality of the 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 the monitoring instruction and the identification information of the target webpage server to the target data processing server;

and 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.

11. The monitoring platform of claim 10, wherein the dispatch 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 webpage server.

12. The monitoring platform of claim 2, wherein the data processing server is further configured to:

determining a target monitoring object and a target monitoring dimension of the nuclear turbine based on the monitoring instruction;

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.

13. 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 operating 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 under the action of centrifugal force, thermal load and gravity load borne by a rotor of the nuclear turbine under multiple working conditions;

acquiring second life monitoring data of low cycle fatigue and creep deformation under the action of pressure and heat load borne by a valve casing and a cylinder of the nuclear power steam turbine under multiple working conditions;

14. 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 operating state data and the load data matched with the safety monitoring instruction and the material performance data, acquiring at least one of the following data:

acquiring first intensity safety monitoring data of power reduction and stress corrosion caused by scaling, abrasion, corrosion and water erosion damage borne by the nuclear turbine;

acquiring second intensity safety monitoring data of steady state and transient state of the rotor of the nuclear turbine under the action of centrifugal force and thermal load;

acquiring third intensity safety monitoring data of steady state and transient state of the pressure and heat load bearing action of a valve casing and a cylinder of the nuclear power turbine;

acquiring safety design monitoring data and safety operation monitoring data of a flange middle facet acted by a cylinder bearing force load, a thermal load and a bolt pre-tightening force load of the nuclear turbine;

15. 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 running state data and the load data matched with the reliability monitoring instruction and the material performance data, acquiring at least one of the following data:

acquiring the monitoring data of the dynamic strength and the vibration reliability of the moving blade of the nuclear turbine under the action of centrifugal force, low-frequency exciting force and high-frequency exciting force;

acquiring torsional vibration reliability monitoring data of a multi-rotor system of the nuclear turbine subjected to power grid electrical disturbance fault;

acquiring first shaft system vibration reliability monitoring data of a rotor and a bearing system of the nuclear turbine under the action of forced vibration and self-excited vibration;