CN114396321B - Multi-dimensional service life monitoring method of nuclear turbine - Google Patents

Multi-dimensional service life monitoring method of nuclear turbine Download PDF

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CN114396321B
CN114396321B CN202111456672.XA CN202111456672A CN114396321B CN 114396321 B CN114396321 B CN 114396321B CN 202111456672 A CN202111456672 A CN 202111456672A CN 114396321 B CN114396321 B CN 114396321B
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life
cylinder
rotor
monitoring data
nuclear
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CN114396321A (en
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史进渊
谢岳生
华浩磊
张义
刘网扣
祝自芳
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Shanghai Power Equipment Research Institute Co Ltd
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Shanghai Power Equipment Research Institute Co Ltd
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Priority to AU2022201697A priority patent/AU2022201697B2/en
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    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
    • F01D—NON-POSITIVE DISPLACEMENT MACHINES OR ENGINES, e.g. STEAM TURBINES
    • F01D21/00—Shutting-down of machines or engines, e.g. in emergency; Regulating, controlling, or safety means not otherwise provided for
    • F01D21/003—Arrangements for testing or measuring

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Abstract

The invention provides a multi-dimensional service life monitoring method and device of a nuclear turbine, electronic equipment and a storage medium, and relates to the technical field of nuclear turbines. The scheme is as follows: 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; generating an optimization improvement strategy of the nuclear power turbine according to at least one abnormal life monitoring data in the first life monitoring data, the second life monitoring data and the third life monitoring data; and optimizing the nuclear turbine according to an optimization and improvement strategy. The method disclosed by the invention can effectively prolong the service life of the nuclear turbine.

Description

Multi-dimensional service life monitoring method of nuclear turbine
Technical Field
The present disclosure relates to the field of nuclear turbine technologies, and in particular, to a method and an apparatus for monitoring a multi-dimensional life of a nuclear turbine, an electronic device, and a storage medium.
Background
The nuclear turbine can bear the action of various damage mechanisms during operation, and the service life of the nuclear turbine is shortened. At present, no method for monitoring the service life of the nuclear turbine under the action of various damage mechanisms exists.
Disclosure of Invention
The disclosure provides a multi-dimensional service life monitoring method and device of a nuclear turbine, electronic equipment and a storage medium.
According to one aspect of the present disclosure, a multi-dimensional life monitoring method for a nuclear turbine is provided, including:
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 wheel 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 shell and the cylinder of the nuclear turbine under the action of quick starting thermal stress under multiple working conditions;
generating an optimization improvement strategy of the nuclear power turbine according to at least one abnormal life monitoring data in the first life monitoring data, the second life monitoring data and the third life monitoring data;
and optimizing the nuclear turbine according to an optimization and improvement strategy.
In the embodiment of the disclosure, the nuclear turbine is subjected to multi-dimensional design monitoring and operation monitoring to obtain a plurality of life monitoring data, and the nuclear turbine is subjected to design optimization or operation optimization based on abnormal life monitoring data, so that the service life of the nuclear turbine can be effectively prolonged under the action of various damage mechanisms.
According to another aspect of the present disclosure, there is provided a multi-dimensional life monitoring apparatus of a nuclear turbine, comprising:
the system comprises a first acquisition module, a second acquisition module and a third acquisition module, wherein the first acquisition module is used for 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 wheel of the nuclear turbine under multiple working conditions;
the second acquisition module is used for acquiring second life monitoring data of low-cycle fatigue and creep deformation under the multi-working condition of pressure bearing and thermal load bearing of a valve shell and a cylinder of the nuclear turbine;
the third acquisition module is used for acquiring third life monitoring data of the rotor, the valve casing and the cylinder of the nuclear turbine under the action of quick starting thermal stress under multiple working conditions;
the generating module is used for generating an optimization improvement strategy of the nuclear power steam turbine according to at least one abnormal life monitoring data in the first life monitoring data, the second life monitoring data and the third life monitoring data;
and the optimization module is used for optimizing the nuclear turbine according to the optimization improvement strategy.
According to another aspect of the present disclosure, there is provided an electronic device comprising a memory, a processor;
the processor runs a program corresponding to the executable program code by reading the executable program code stored in the memory, so as to implement the multidimensional life monitoring method for the nuclear power turbine according to the embodiment of the first aspect of the present disclosure.
According to another aspect of the present disclosure, there is provided a computer readable storage medium having stored thereon a computer program which, when executed by a processor, implements a multi-dimensional life monitoring method of a nuclear power turbine in accordance with an embodiment of the first aspect of the present disclosure.
According to another aspect of the present disclosure, a computer program product is provided, comprising a computer program which, when executed by a processor, implements a multi-dimensional life monitoring method of a nuclear power turbine according to an embodiment of the first aspect of the present disclosure.
It should be understood that the statements in this section do not necessarily identify key or critical features of the embodiments of the present disclosure, nor do they limit the scope of the present disclosure. Other features of the present disclosure will become apparent from the following description.
Drawings
FIG. 1 is a schematic illustration of a combined monitoring platform for a nuclear turbine;
FIG. 2 is a flow chart of a multi-dimensional life monitoring method of a nuclear power turbine according to one embodiment of the present disclosure;
FIG. 3 is a flow chart of a multi-dimensional life monitoring method of a nuclear power turbine according to one embodiment of the present disclosure;
FIG. 4 is a flow chart of a multi-dimensional life monitoring method of a nuclear power turbine according to one embodiment of the present disclosure;
FIG. 5 is a flow chart of a multi-dimensional life monitoring method of a nuclear power turbine according to one embodiment of the present disclosure;
FIG. 6 is a flow chart of a multi-dimensional life monitoring method of a nuclear power turbine according to one embodiment of the present disclosure;
FIG. 7 is a flow chart of a multi-dimensional life monitoring method of a nuclear power turbine according to one embodiment of the present disclosure;
FIG. 8 is a flow chart of a multi-dimensional life monitoring method for a nuclear power turbine according to one embodiment of the present disclosure;
FIG. 9 is a flow chart of a multi-dimensional life monitoring method of a nuclear power turbine according to one embodiment of the present disclosure;
FIG. 10 is a block diagram of a multi-dimensional life monitoring device for a nuclear power turbine according to one embodiment of the present disclosure;
FIG. 11 is a block diagram of electronic equipment used to implement the multi-dimensional life monitoring method of a nuclear turbine according to an embodiment of the present disclosure.
Detailed Description
Reference will now be made in detail to embodiments of the present invention, 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 function throughout. The embodiments described below with reference to the drawings are illustrative and intended to be illustrative of the invention and are not to be construed as limiting the invention.
FIG. 1 is a combined monitoring platform for a nuclear turbine according to an embodiment of the present application, as shown in FIG. 1, including:
component model library servers, load database servers, material database servers, compute servers, web servers, and client browsers.
The method comprises the steps that a component model library server stores component design parameters and a three-dimensional mechanical model of the nuclear turbine, a load database server stores pressure load, centrifugal force load, thermal load, bolt pretightening force load, rigidity coefficient and damping coefficient of a bearing oil film, metal temperature of a measuring point at the depth of 85% -95% of the wall thickness of an inner cylinder, metal temperature of a measuring point at the depth of 85% -95% of the wall thickness of a valve shell and a cylinder, metal temperature of a measuring point at the depth of 45% -50% of the wall thickness of the valve shell and the cylinder, and start-stop curves of the nuclear turbine, a material database server stores material physical property, material mechanical property, high-temperature long-time mechanical property and fatigue fracture mechanical property of the nuclear turbine, a computing server comprises a memory, a processor and a monitoring computer program which is stored on the memory and can run on the processor, and when the processor executes the computer program, the multi-dimensional life monitoring method of the nuclear turbine is achieved.
The component model data 1, the load database 2 and the material database 3 are in communication connection with the calculation server and are used for sending mechanical models and data required by monitoring the nuclear turbine in different targets and dimensions to the calculation server 4;
the calculation server 4 is in communication connection with the web server 5, the web server 5 is in communication connection with the client browser 6, and monitoring data or optimization information can be fed back to the web server 5 and the client browser 6 for display.
The method, the device, the electronic equipment and the storage medium for monitoring the service life of the nuclear turbine under the action of the rapid-start thermal stress are described in the following with reference to the attached drawings.
FIG. 2 is a flow chart of a method for multi-dimensional life monitoring of a nuclear power turbine according to one embodiment of the present disclosure, as shown in FIG. 2, the method including the steps of:
s201, 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.
The first life monitoring data is used for determining whether the design monitoring of the low cycle fatigue and high cycle fatigue life of the rotor of the nuclear turbine under the action of centrifugal force, thermal load and gravity load is qualified or not.
In some implementations, the first life monitoring data is monitoring data of a weak life portion of the rotor.
Optionally, when the first life monitoring data is greater than or equal to 60 years, the low cycle fatigue and high cycle fatigue life design monitoring is qualified, and the low cycle fatigue and high cycle fatigue life design of the life weak part of the nuclear turbine rotor is in a controlled state.
Optionally, when the first life monitoring data is less than 60 years, the low cycle fatigue and high cycle fatigue life design monitoring is unqualified, which indicates that the materials and the structure of the nuclear turbine need to be optimized and improved in the design stage.
S202, second life monitoring data of low-cycle fatigue and creep under the action of pressure and heat load borne by a valve shell and a cylinder of the nuclear turbine under multiple working conditions are obtained.
And the second life monitoring data is used for determining whether the design monitoring of the low-cycle fatigue and creep life of the valve casing and the cylinder bearing pressure and thermal load action of the nuclear turbine is qualified or not.
In some implementations, the second life monitoring data is monitoring data of valve housing and weak part of life of the cylinder.
Optionally, when the second life monitoring data is greater than or equal to 60 years, the low cycle fatigue and creep life design monitoring is qualified, and the low cycle fatigue and creep life design of the valve casing and the weak life part of the cylinder of the nuclear turbine is in a controlled state.
Optionally, when the second life monitoring data is less than 60 years, the low cycle fatigue and creep life design monitoring is unqualified, which indicates that the materials and the structure of the nuclear turbine need to be optimized and improved in the design stage.
S203, acquiring third life monitoring data of the rotor, the valve casing and the cylinder of the nuclear turbine under the action of quick starting thermal stress under multiple working conditions.
And the third life monitoring data is used for determining whether the life monitoring of the rotor, the valve casing and the cylinder of the nuclear turbine bearing the rapid starting thermal stress is qualified or not.
Optionally, when the third life monitoring data is less than 1, the life monitoring is qualified, which indicates that the life of the rotor, the valve casing and the cylinder of the nuclear turbine subjected to the rapid starting thermal stress is in a controlled state.
Optionally, when the third life monitoring data is greater than or equal to 1, the life monitoring is unqualified, which indicates that the starting process of the nuclear turbine needs to be optimized and improved in the operation stage.
And S204, generating an optimization improvement strategy of the nuclear turbine according to at least one abnormal life monitoring data in the first life monitoring data, the second life monitoring data and the third life monitoring data.
And judging whether the acquired first life monitoring data, second life monitoring data and third life monitoring data meet monitoring qualified conditions, and if abnormal life monitoring data which do not meet the monitoring qualified conditions exist, generating an optimization improvement strategy of the nuclear turbine based on the abnormal life monitoring data.
For example, if the abnormal life monitoring data is the first life monitoring data, generating a design optimization improvement strategy of the nuclear power turbine rotor; and if the abnormal life monitoring data is the third life monitoring data, generating an optimization and improvement strategy of the starting process of the nuclear power turbine.
The abnormal life monitoring data may be one or more.
S205, optimizing the nuclear turbine according to an optimization and improvement strategy.
Optionally, the optimization and improvement strategy comprises an adjusting component and an adjusting parameter of the nuclear turbine, and the nuclear turbine can be optimized according to the adjusting component and the adjusting parameter.
In the embodiment of the disclosure, 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 wheel of a nuclear turbine under multiple working conditions are acquired, second life monitoring data of low-cycle fatigue and creep under the action of pressure and thermal load borne by a valve casing and a cylinder of the nuclear turbine under multiple working conditions are acquired, third life monitoring data under the action of quick starting thermal stress borne by a rotor, the valve casing and the cylinder of the nuclear turbine under multiple working conditions are acquired, an optimization improvement strategy of the nuclear turbine is generated according to at least one abnormal life monitoring data in the first life monitoring data, the second life monitoring data and the third life monitoring data, and the nuclear turbine is optimized according to the optimization improvement strategy. In the embodiment of the disclosure, the nuclear turbine is subjected to multi-dimensional design monitoring and operation monitoring to obtain a plurality of life monitoring data, and the nuclear turbine is subjected to design optimization or operation optimization based on abnormal life monitoring data, so that the service life of the nuclear turbine can be effectively prolonged under the action of various damage mechanisms.
Fig. 3 is a flow chart of a multi-dimensional life monitoring method for a nuclear power turbine according to an embodiment of the present disclosure, and based on the above embodiment, with further reference to fig. 3, a process of generating an optimization improvement strategy for a nuclear power turbine and optimizing the nuclear power turbine according to the optimization improvement strategy is explained, including the following steps:
s301, judging whether the nuclear power turbine meets monitoring qualified conditions or not according to the first service life monitoring data, the second service life monitoring data and the third service life monitoring data.
And judging whether the nuclear turbine meets the monitoring qualified conditions or not according to the numerical values of the first service life monitoring data, the second service life monitoring data and the third service life monitoring data.
Optionally, the monitoring qualified condition of the first life monitoring data is that the numerical value is greater than or equal to 60 years, the monitoring qualified condition of the second life monitoring data is that the numerical value is greater than or equal to 60 years, and the monitoring qualified condition of the third life monitoring data is that the numerical value is less than 1.
S302, if one of the life monitoring data does not meet the monitoring qualified condition, generating an optimization improvement strategy of the nuclear turbine based on the abnormal life monitoring data which does not meet the monitoring qualified condition.
If the service life monitoring data do not meet the monitoring qualified conditions, the service life monitoring data are abnormal service life monitoring data, the part to which the abnormal service life monitoring data belong is obtained, the optimization model of the nuclear turbine is called based on the part to which the abnormal service life monitoring data belong, and the optimization improvement strategy of the nuclear turbine is generated based on the optimization model.
The optimization and improvement strategy can comprise changing materials with better mechanical property, and optimizing material design, structure size, structure fillet, inlet steam temperature change rate and the like.
For example, if the value of the first life monitoring data is less than 60 years, the abnormal life monitoring data is the first life monitoring data, the component to which the abnormal life monitoring data belongs is a rotor of the nuclear turbine, and an optimization model of the rotor is called to generate a design optimization improvement strategy of the nuclear turbine.
For example, if the value of the third life monitoring data is greater than 1, the abnormal life monitoring data is the third life monitoring data, the component to which the abnormal life monitoring data belongs is the starting process of the nuclear turbine, the optimization model of the starting process is called, and the operation optimization improvement strategy of the nuclear turbine is generated.
And S303, acquiring an adjusting part of the nuclear turbine according to an optimization and improvement strategy.
The optimization and improvement strategy comprises an adjusting component of the nuclear turbine, wherein the adjusting component is a component to which abnormal life monitoring data belongs in the embodiment.
When the abnormal life monitoring data is the first life monitoring data, the adjusting component is a rotor of the nuclear turbine; when the abnormal life monitoring data is second life monitoring data, the adjusting component is a valve shell and a cylinder of the nuclear turbine; and when the abnormal life monitoring data is third life monitoring data, the adjusting component is the starting process of the nuclear turbine.
S304, optimizing the adjusting component according to the adjusting parameters of the adjusting component in the optimization and improvement strategy.
And performing design optimization or operation optimization on the adjusting component according to the adjusting parameters of the adjusting component in the optimization and improvement strategy.
In some implementations, a rotor of a nuclear turbine is designed and optimized according to the tuning parameters.
In other implementations, valve casings and cylinders of a nuclear turbine are designed and optimized according to adjustment parameters.
In other implementations, the startup process of the nuclear turbine is optimized for operation based on the tuning parameters.
And S305, continuing to monitor the abnormal life monitoring data which do not meet the monitoring qualified conditions, if the newly acquired life monitoring data still do not meet the monitoring qualified conditions, updating the optimization improvement strategy, and continuing to optimize the adjusting component based on the updated optimization improvement strategy.
Continuing to monitor the abnormal life monitoring data which do not meet the monitoring qualified conditions, and if the newly acquired life monitoring data meet the monitoring qualified conditions, ending the monitoring; and if the newly acquired life monitoring data still does not meet the monitoring qualified conditions, increasing the optimization strength of the optimization improvement strategy, updating the optimization improvement strategy, and continuously optimizing the adjusting part based on the updated optimization improvement strategy until the life monitoring data meets the monitoring qualified conditions.
In the embodiment of the disclosure, whether a nuclear turbine meets monitoring qualified conditions is judged according to first life monitoring data, second life monitoring data and third life monitoring data, if one of the life monitoring data does not meet the monitoring qualified conditions, an optimization improvement strategy of the nuclear turbine is generated based on abnormal life monitoring data which does not meet the monitoring qualified conditions, an adjusting component of the nuclear turbine is obtained according to the optimization improvement strategy, the adjusting component is optimized according to adjusting parameters of the adjusting component in the optimization improvement strategy, monitoring is continuously performed on the abnormal life monitoring data which does not meet the monitoring qualified conditions after optimization, if the newly obtained life monitoring data still does not meet the monitoring qualified conditions, the optimization improvement strategy is updated, and the adjusting component is continuously optimized based on the updated optimization improvement strategy. In the embodiment of the disclosure, an optimization and improvement strategy is generated based on abnormal life monitoring data and the nuclear turbine is optimized, so that main factors influencing the long-life operation of the nuclear turbine are improved in a targeted manner, and the service life of the nuclear turbine reaches a qualified condition.
Fig. 4 is a flowchart of a multi-dimensional life monitoring method for a nuclear turbine according to an embodiment of the present disclosure, and based on the above embodiment, with reference to fig. 4, a process of designing and monitoring a rotor life is explained, which includes the following steps:
and S401, determining a life weak part of the rotor.
Based on a component model library server, a load database server and a material database server, 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 are input, a method and a subprogram for designing and monitoring low cycle fatigue and high cycle fatigue life are used, and a part with the maximum amplitude of high cycle fatigue stress under a steady rated working condition is determined to be used as a weak part of the life of the nuclear turbine rotor.
S402, acquiring first crack initiation life parameters of low cycle fatigue and high cycle fatigue of the rotor life weak part.
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 library server, a load database server and a material database server, and calculating the cold start-stop low-cycle fatigue crack initiation life N of the weak part of the nuclear turbine rotor by using a method and a subprogram for designing and monitoring the low-cycle fatigue and the high-cycle fatigue life ic Low cycle fatigue crack initiation life N iw Thermal start-stop low cycle fatigue crack initiation life N ih And low cycle fatigue crack initiation life N in 110% overspeed test process i110 High cycle fatigue crack initiation life N of rotor iH 。
Wherein N is calculated ic 、N iw 、N ih 、N i110 、N iH Is a first crack initiation life parameter.
And S403, acquiring first crack propagation life parameters of low-cycle fatigue and high-cycle fatigue of the rotor life weak part.
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 library server, a load database server and a material database server, and calculating to obtain a first-stage cold-start low-cycle fatigue crack propagation 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,1 First stage warm start low cycle fatigue crack propagation life N pw,1 First stage hot start low cycle fatigue crack propagation life N ph,1 First stage normal shutdown low cycle fatigue crack propagation life N pn,1 First stage 110% overspeed test low cycle fatigue crack propagation life N p110,1 Second stage ofLow cycle fatigue crack propagation life N for cold start pc,2 Second-stage warm start low cycle fatigue crack propagation life N pw,2 Second stage hot start low cycle fatigue crack propagation life N ph,2 Second stage normal shutdown low cycle fatigue crack propagation life N pn,2 110% overspeed test low cycle fatigue crack propagation life N p110,2 High cycle fatigue crack propagation life N of rotor pH 。
Wherein N is calculated pc,1 、N pw,1 、N ph,1 、N pn,1 、N p110,1 、N pc,2 、N pw,2 、N ph,2 、N pn,2 、N p110,2 、N pH Is a first crack propagation life parameter.
S404, determining first life monitoring data according to the first crack initiation life parameter and the first crack propagation life parameter.
The method comprises the steps of obtaining first operation state data of the nuclear turbine with the rotor bearing the effects of centrifugal force, thermal load and gravity load under multiple working conditions, determining the total service life of the outer surface of the rotor and the total service life of the inner surface and the inner part of the rotor according to the first operation state data, a first crack initiation service life parameter and a first crack propagation service life parameter, and determining the total service life of the rotor according to the total service life of the outer surface of the rotor and the total service life of the inner surface and the inner part of the rotor. Wherein the total life of the rotor is the first life monitoring data.
Method and subprogram for designing and monitoring low-cycle fatigue and high-cycle fatigue life based on load database server to obtain annual average cold starting times y of nuclear turbine c Annual average temperature state starting times y w Annual average thermal state number of starts y h Number of normal annual stoppages y n Annual average 110% number of overspeed tests y 110 Annual average operating hours t y Working speed n 0 . Wherein y is obtained c 、y w 、y h 、y n 、y 110 、t y 、n 0 Is the first operating state data.
Based on the first operating condition data, the first crackAnd performing arithmetic operation on the initiation life parameter and the first crack propagation life parameter to obtain the total service life of the outer surface and the total service life of the inner surface of the rotor. Firstly, calculating the annual average high cycle fatigue times y of the nuclear turbine rotor H ，
Figure GDA0003638870840000051
Total service life tau of rotor outer surface of nuclear power turbine CLto The calculation formula of (2) is as follows.
Figure GDA0003638870840000061
Total service life tau of inner surface and interior of nuclear turbine rotor CLti Is calculated by the formula
Figure GDA0003638870840000062
The total life of the rotor being determined by the lesser of the total life of the inner and inner surfaces of the rotor and the total life of the outer surface, i.e. the total life τ of the rotor CLt ＝min{τ CLto ,τ CLti }。
S405, responding to the condition that the first life monitoring data does not meet the monitoring qualified condition, and generating an optimization improvement strategy of the nuclear turbine rotor.
Optionally, the monitoring qualified condition is that the first life monitoring data is greater than or equal to 60 years, and when the first life monitoring data is less than 60 years, an optimization improvement strategy of the nuclear power turbine rotor is generated.
Optionally, the optimization and improvement strategy of the rotor may include the material type, material design, structural size, structural fillet, etc. of the rotor.
S406, the rotor is optimized according to the optimization improvement strategy, the first life monitoring data is continuously monitored, if the first life monitoring data obtained again does not meet the monitoring qualified conditions, the optimization improvement strategy is updated, and the rotor is continuously optimized based on the updated optimization improvement strategy.
The method comprises the steps of optimizing a rotor according to an optimization improvement strategy, updating design parameters, a three-dimensional mechanical model and material performance data of the rotor, obtaining a newly generated first crack initiation life parameter and a first crack propagation life parameter, and monitoring first life monitoring data determined based on the newly generated first crack initiation life parameter and the first crack propagation life parameter.
If the first service life monitoring data acquired again meet the qualified monitoring conditions, ending the design monitoring of the service life of the rotor; if the first life monitoring data acquired again does not meet the monitoring qualified conditions, updating an optimization improvement strategy, optionally, replacing the material type of the rotor with a material with better mechanical property, or changing the material design, the structural size, the structural fillet and the like of the rotor.
And optimizing the rotor based on the updated optimization improvement strategy, continuously monitoring the first life monitoring data, updating the optimization improvement strategy again and optimizing the rotor when the first life monitoring data does not meet the monitoring qualified conditions until the first life monitoring data meets the monitoring qualified conditions.
In the embodiment of the disclosure, a life weak part of a rotor is determined, a first crack initiation life parameter and a first crack propagation life parameter of low-cycle fatigue and high-cycle fatigue of the life weak part of the rotor are obtained, first life monitoring data are determined according to the first crack initiation life parameter and the first crack propagation life parameter, an optimization improvement strategy of the rotor of the nuclear power turbine is generated in response to the fact that the first life monitoring data do not meet monitoring qualified conditions, the rotor is optimized according to the optimization improvement strategy, the first life monitoring data are continuously monitored, if the first life monitoring data obtained again do not meet the monitoring qualified conditions, the optimization improvement strategy is updated, and the rotor is continuously optimized based on the updated optimization improvement strategy. In the embodiment of the disclosure, the first life monitoring data is obtained, and the rotor is optimized when the first life monitoring data does not meet the monitoring qualified condition, so that the service life of the rotor of the nuclear turbine can reach the qualified condition.
Fig. 5 is a flowchart of a multidimensional service life monitoring method for a nuclear turbine according to an embodiment of the present disclosure, and as shown in fig. 5, based on the service life monitoring method provided by the present disclosure, a process of designing and monitoring that a low cycle fatigue life and a high cycle fatigue life of a rotor subjected to centrifugal force, thermal load and gravity load reach 60 years under an actual application scenario includes the following steps:
s501, determining the starting and stopping times of the nuclear turbine.
A method and a subprogram for designing and monitoring low-cycle fatigue and high-cycle fatigue life are used for inputting the annual average cold-state starting times y of a nuclear turbine based on a load database server 2 c Annual average temperature state starting times y w Annual average thermal state number of starts y h Number of normal annual stoppages y n Annual average 110% number of overspeed tests y 110 Annual average operating hours t y Working speed n 0 . The number of times of starting and stopping the nuclear turbine is the first operation state data in the embodiment.
For example, for a 1200MW nuclear turbine, the annual average cold start times y of the 1200MW nuclear turbine are input based on the load database server 2 c Annual average temperature state starting times y w Annual average thermal state number of starts y h Number of normal annual stoppages y n Annual average 110% number of overspeed tests y 110 Annual average operating hours t y Working speed n 0 The specific 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 c Once/time 4
2 Number of annual mean temperature state starts y w Once/time 20
3 Number of annual average thermal state starts y h Once/time 75
4 Number of annual average normal stops y n Once/time 99
5 Annual average 110% number of overspeed tests y 110 Once/time 1
6 Number of annual average operating hours t y /h 7000
7 Operating speed n 0 /r/min 1500
S502, calculating first crack initiation life parameters of low cycle fatigue and high cycle fatigue of the nuclear turbine rotor.
Inputting design parameters and three-dimensional mechanics of a nuclear turbine rotor based on a component model library server 1, a load database server 2 and a material database server 3The method comprises the steps of determining a part with the maximum steady-state rated working condition high cycle fatigue stress amplitude as a weak life part of the nuclear steam turbine rotor by using a low cycle fatigue and high cycle fatigue life design monitoring method and a subprogram of the centrifugal force, the thermal load and the gravity load of a nuclear steam turbine rotor and blades and material performance data, and calculating the cold start-stop low cycle fatigue crack initiation life N of the weak life part of the nuclear steam turbine rotor ic Low cycle fatigue crack initiation life N at start and stop at temperature iw Thermal start-stop low cycle fatigue crack initiation life N ih And a low cycle fatigue crack initiation life N in 110% overspeed test i110 And 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-state rated working condition is determined as a weak life part of the rotor of the 1200MW nuclear power turbine, the weak life part is a round corner part of the root 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 ic Low cycle fatigue crack initiation life N at start and stop at temperature iw Thermal start-stop low cycle fatigue crack initiation life N ih And a low cycle fatigue crack initiation life N in 110% overspeed test i110 And rotor high cycle fatigue crack initiation life N iH The specific 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 i Once/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 ＝9.5×10 9
S503, calculating first crack propagation life parameters of low cycle fatigue and 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 library server 1, a load database server 2 and a material database server 3, and calculating a first-stage cold-start low-cycle fatigue crack propagation 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,1 First stage warm start low cycle fatigue crack propagation life N pw,1 First stage hot start low cycle fatigue crack propagation life N ph,1 The first stage of normal shutdown for a low cycleFatigue crack propagation life N pn,1 First stage 110% overspeed test low cycle fatigue crack propagation life N p110,1 Second stage cold start low cycle fatigue crack propagation life N pc,2 Second stage warm start low cycle fatigue crack propagation life N pw,2 Second stage hot start low cycle fatigue crack propagation life N ph,2 Second stage normal shutdown low cycle fatigue crack propagation life N pn,2 110% overspeed test low cycle fatigue crack propagation life N p110,2 And 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,1 First-stage warm-start low-cycle fatigue crack propagation life N pw,1 First stage thermal Start Low cycle fatigue crack propagation Life N ph,1 First stage normal shutdown low cycle fatigue crack propagation life N pn,1 First stage 110% overspeed test low cycle fatigue crack propagation life N p110,1 Second stage cold start low cycle fatigue crack propagation life N pc,2 Second-stage warm start low cycle fatigue crack propagation life N pw,2 Second stage hot start low cycle fatigue crack propagation life N ph,1 Second stage normal shutdown low cycle fatigue crack propagation life N pn,2 110% overspeed test low cycle fatigue crack propagation life N p110,2 And rotor high cycle fatigue crack propagation life N pH The specific results are shown in Table 3;
TABLE 3 rotor Low cycle fatigue and high cycle fatigue crack propagation life N pi
Figure GDA0003638870840000081
And S504, calculating annual high cycle fatigue times of the nuclear turbine rotor.
Annual average high cycle fatigue times y of nuclear turbine rotor H Calculated according to the following formula:
Figure GDA0003638870840000082
wherein, t y The annual average operating hours of the nuclear turbine, n 0 The working rotating speed is set;
for example, the annual average high cycle fatigue times y of the 1200MW nuclear turbine rotor H Calculated according to the following formula:
Figure GDA0003638870840000083
in the above formula, t y 7000h and n for annual average running hours of nuclear power steam turbine 0 The working speed is 1500r/min.
And S505, calculating the total service life of the outer surface of the rotor of the nuclear turbine.
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 CLts Calculated according to the following formula:
Figure GDA0003638870840000084
s506, calculating the total service life of the inner surface and the interior of the nuclear turbine rotor.
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 S507, determining the total service life of the nuclear turbine rotor.
For example, the model 1200MW coreTotal life τ of electric turbine rotor CLt Calculated according to the following formula:
τ CLt ＝min{τ CLts ,τ CLti }＝min{τ CLts ,τ CLti ＞τ CLts }＝τ CLts =66.74 years
And S508, optimally controlling the low-cycle fatigue and high-cycle fatigue life of the nuclear turbine rotor.
The optimization control comprises monitoring the total service life of the nuclear turbine rotor, generating a design optimization improvement strategy of the nuclear turbine in response to the condition that the total service life does not meet the qualified condition, optimizing the rotor based on the optimization improvement strategy, and executing S501-S508 again until the total service life of the rotor is more than or equal to 60 years.
For example, the low cycle fatigue and the high cycle fatigue life of the rotor of the 1200MW nuclear turbine are optimally designed and controlled:
due to tau CLt And the year of 66.74 is more than 60 years, the design monitoring of the low cycle fatigue and the high cycle fatigue life of the 1200MW nuclear turbine rotor bearing the centrifugal force, the thermal load and the gravity load is qualified, the low cycle fatigue and the high cycle fatigue life of the 1200MW nuclear turbine rotor are in a controlled state, the design monitoring of the low cycle fatigue and the high cycle fatigue life of the 1200MW nuclear turbine rotor is finished, and the process of monitoring the design 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 optimized 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.
Fig. 6 is a flow chart of a multi-dimensional life monitoring method for a nuclear turbine according to an embodiment of the present disclosure, and further with reference to fig. 5, a process of designing and monitoring the life of the valve casing and the cylinder is explained on the basis of the above embodiment, which includes the following steps:
and S601, determining a life weak part of the valve shell and the cylinder.
Based on a component model library server, a load database server and a material database server of the nuclear turbine, design parameters and a three-dimensional mechanical model of the nuclear turbine, pressure and thermal load of a nuclear turbine valve casing and a cylinder and material performance data are input, and a method and a subprogram for designing and monitoring low cycle fatigue and creep life are used for determining a maximum part of surface transient stress as a weak part of the life of the nuclear turbine valve casing and the cylinder.
And S602, acquiring second crack initiation life parameters of low cycle fatigue and creep of the valve shell and the cylinder life weak part.
Based on a component model library server, a load database server and a material database server of the nuclear turbine, design parameters and a three-dimensional mechanical model of the nuclear turbine, pressure and thermal load of a nuclear turbine valve shell and a cylinder and material performance data are input, and a method and a subprogram for designing and monitoring low cycle fatigue and creep life are used for calculating to obtain the cold start-stop low cycle fatigue crack initiation life N of the nuclear turbine valve shell and the weak part of the cylinder in service life c Low cycle fatigue crack initiation life N at start and stop at temperature w Thermal start-stop low cycle fatigue crack initiation life N h And creep crack initiation life tau of valve housing and cylinder c 。
Inlet temperature of pressurized water reactor nuclear steam turbine<At 300 ℃, the valve shell and the cylinder do not creep, and the creep crack initiation life tau is processed c Infinity, but the steam admission 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 。
Wherein N is calculated c 、N w 、N h 、τ c Is a second crack initiation life parameter.
And S603, acquiring second crack propagation life parameters of low cycle fatigue and creep of the valve shell and the cylinder life weak part.
Inputting design parameters and 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 based on a component model library server, a load database server and a material database server of the nuclear turbine, and using low-cycle dataMethod and subprogram for designing and monitoring fatigue and creep life, calculating to obtain the cold-start low-cycle fatigue crack propagation life N of the weak part of the life of valve casing and cylinder of nuclear turbine fc Low cycle fatigue crack propagation life N for warm start fw Thermal start low cycle fatigue crack propagation life N fh Normal shutdown low cycle fatigue crack propagation life N fn And creep crack propagation life tau of valve housing and cylinder fc 。
Inlet temperature of pressurized water reactor nuclear steam turbine<At 300 ℃, the valve shell and the cylinder do not creep, and the creep crack is processed to extend the life tau fc Infinity, but the steam admission 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 a valve shell and a cylinder needs to be calculated fc 。
Wherein N is calculated fc 、N fw 、N fh 、N fn 、τ fc Is a second crack propagation life parameter.
S604, determining second life monitoring data according to the second crack initiation life parameter and the second crack propagation life parameter.
The method comprises the steps of obtaining second operation state data of the nuclear turbine bearing pressure and heat load under multiple working conditions of the valve casing and the cylinder, determining the total service life of the outer surface of the valve casing and the cylinder and the total service life of the inner surface of the valve casing and the cylinder according to the second operation state data, second crack initiation life parameters and second crack extension life parameters, and determining the total service life of the valve casing and the cylinder according to the total service life of the outer surface of the valve casing and the cylinder and the total service life of the inner surface of the valve casing and the cylinder. Wherein the total life of the valve housing and the cylinder is the second life monitoring data.
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 server to obtain annual cold-state starting times y of nuclear turbine c Annual average temperature state starting times y w Annual average thermal state number of starts y h Number of normal annual stoppages y n Annual average operating hours t y . Wherein y is obtained c 、y w 、y h 、y n 、t y Is the second operating state data.
And performing arithmetic operation based on the second operating state data, the second crack initiation life parameter and the second crack propagation life parameter to obtain the total service life of the outer surface and the total service life of the inner surface of the valve shell and the cylinder.
Total service life tau of valve casing and outer surface of cylinder of nuclear turbine CLtoc Is calculated by the formula
Figure GDA0003638870840000101
Total service life tau of valve casing and outer surface of cylinder of nuclear turbine CLtic Is calculated by the formula
Figure GDA0003638870840000102
The total life of the valve housing and cylinder being determined by the lesser of the total life of the valve housing and cylinder inner surface and the total life of the outer surface, i.e. the total life of the valve housing and cylinder τ CLtc ＝min{τ CLtoc ,τ CLtic }
And S605, responding to the second service life monitoring data which do not meet the qualified monitoring conditions, and generating an optimization and improvement strategy of the valve shell and the cylinder of the nuclear turbine.
Optionally, the monitoring qualified condition is that the second life monitoring data is greater than or equal to 60 years, and when the second life monitoring data is less than 60 years, an optimized improvement strategy of the valve shell and the cylinder of the nuclear power turbine is generated.
Optionally, the valve housing and cylinder optimization improvement strategy may include valve housing and cylinder material type, material design, structural dimensions and structural fillets, and the like.
And S606, optimizing the valve shell and the cylinder according to the optimization improvement strategy, continuously monitoring second life monitoring data, updating the optimization improvement strategy if the second life monitoring data acquired again still does not meet the monitoring qualified conditions, and continuously optimizing the valve shell and the cylinder based on the updated optimization improvement strategy.
And optimizing the valve shell and the cylinder according to an optimization improvement strategy, updating design parameters, a three-dimensional mechanical model and material performance data of the valve shell and the cylinder, acquiring a newly generated second crack initiation life parameter and a second crack propagation life parameter, and monitoring second life monitoring data determined based on the newly generated second crack initiation life parameter and the second crack propagation life parameter.
If the second service life monitoring data acquired again meet the monitoring qualified conditions, ending the design monitoring of the service lives of the valve shell and the cylinder; if the second life monitoring data acquired again still does not meet the monitoring qualified conditions, updating the optimization improvement strategy, optionally, replacing the material types of the valve shell and the cylinder with materials with better mechanical properties, or changing the material design, the structural size, the structural fillet and the like of the valve shell and the cylinder.
Optimizing the valve casing and the cylinder based on the updated optimization improvement strategy, continuously monitoring second life monitoring data, updating the optimization improvement strategy again when the second life monitoring data do not meet the monitoring qualified conditions, and optimizing the valve casing and the cylinder until the second life monitoring data meet the monitoring qualified conditions.
In the embodiment of the disclosure, the maximum position of the transient stress on the surface is determined as a life weak position of the valve casing and the cylinder, a second crack initiation life parameter and a second crack propagation life parameter of low cycle fatigue and creep of the life weak position of the valve casing and the cylinder are obtained, second life monitoring data are determined according to the second crack initiation life parameter and the second crack propagation life parameter, an optimization improvement strategy of the valve casing and the cylinder of the nuclear turbine is generated in response to the situation that the second life monitoring data do not meet a monitoring qualified condition, the valve casing and the cylinder are optimized according to the optimization improvement strategy, the second life monitoring data are continuously monitored, if the second life monitoring data obtained again do not meet the monitoring qualified condition, the optimization improvement strategy is updated, and the valve casing and the cylinder are continuously optimized based on the updated optimization improvement strategy. In the embodiment of the disclosure, second life monitoring data is acquired, and the valve casing and the cylinder are optimized when the second life monitoring data does not meet the monitoring qualified conditions, so that the service lives of the valve casing and the cylinder of the nuclear power turbine can reach the qualified conditions.
Fig. 7 is a flowchart of a multidimensional life monitoring method for a nuclear turbine according to an embodiment of the present disclosure, and as shown in fig. 7, based on the life monitoring method provided by the present disclosure, in an actual application scenario, a process of designing and monitoring a low cycle fatigue and a creep life of a valve casing and a cylinder under pressure and thermal load effects for 60 years includes the following steps:
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 are used, based on load database server, annual average cold state starting times y of nuclear turbine are input c Annual average temperature state starting times y w Annual average thermal state number of starts y h Number of normal annual stoppages y n Annual average operating hours t y (ii) a The number of times of starting and stopping the nuclear turbine is the second operation state data in the embodiment.
For example, for a certain model 1200MW nuclear turbine, the annual average cold state starting times y of the model 1200MW nuclear turbine is input based on the load database server 2 c Annual average temperature state starting times y w Annual average thermal state number of starts y h Number of normal annual stoppages y n Annual average operating hours t y Specific results are shown in Table 4;
TABLE 4 number of starts and stops of steam turbine
Serial number Item Index value
1 Number of cold-state annual starts y c Once/time 4
2 Number of annual mean temperature state starts y w Once/time 20
3 Number of annual average thermal state starts y h Once/time 75
4 Number of annual average normal stops y n Once/time 99
5 Number of annual average operating hours t y /h 7000
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, pressure and thermal load of a nuclear turbine valve shell and a cylinder and material performance data, determining a weak service life part of the nuclear turbine valve shell and the cylinder by using a low-cycle fatigue and creep life design monitoring method and subprogram, and calculating to obtain a cold start-stop low-cycle fatigue crack initiation life N of the weak service life part of the nuclear turbine valve shell and the cylinder c Low cycle fatigue crack initiation life N at start and stop at temperature w Low cycle fatigue from start to stop in hot stateCrack initiation life N h And 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 c Infinity ∞ 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 library server 1, a load database server 2 and a material database server 3 of a nuclear turbine, design parameters and a three-dimensional mechanical model of the 1200MW nuclear turbine, pressure and thermal load of a valve casing and a cylinder of the 1200MW nuclear turbine and material performance data are input, a low cycle fatigue and creep life design monitoring method is used, the weak part of the service life of the valve casing and the cylinder of the 1200MW nuclear turbine is determined to be the transition fillet of an inner cylinder outer surface steam inlet pipe and an inner cylinder at the steam inlet side with the maximum transient stress, and the cold start-stop low cycle fatigue crack initiation life N of the weak part of the valve casing and the cylinder of the 1200MW nuclear turbine is calculated c Low cycle fatigue crack initiation life N at start and stop at temperature w Thermal start-stop low cycle fatigue crack initiation life N h The results are shown in Table 5, since this model 1200MW nuclear turbine is a pressurized water reactor nuclear turbine, the admission temperature t is 01 =280.3 ℃, the creep of the valve casing and the cylinder does not occur (for the four-generation nuclear power turbine such as the high-temperature gas cooled reactor, the creep life damage must be considered because the steam inlet temperature is more than 500 ℃), and the creep crack initiation life tau of the weak part of the life is processed c Infinity ∞ 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
Figure GDA0003638870840000111
Figure GDA0003638870840000121
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 library server 1, a load database server 2 and a material database server 3 of the nuclear power turbine, design parameters and a three-dimensional mechanical model of the nuclear power turbine, pressure and thermal load of a valve shell and a cylinder of the nuclear power turbine and material performance data are input, and a method and a subprogram for designing and monitoring low cycle fatigue and creep life are used for calculating cold-start low cycle fatigue crack extension life N of the valve shell of the nuclear power turbine and a weak life part of the cylinder fc Low cycle fatigue crack propagation life N for warm start fw Thermal start low cycle fatigue crack propagation life N fh Normal shutdown low cycle fatigue crack propagation life N fn And 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 fc Infinity ∞ 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 library server, a load database server and a material database server of a nuclear turbine, design parameters and a three-dimensional mechanical model of the 1200MW nuclear turbine, pressure and thermal load of a valve casing and a cylinder of the 1200MW nuclear turbine and material performance data are input, and a low cycle fatigue and creep life design monitoring method is used for calculating cold starting low cycle fatigue crack extension life N of a weak life part of the valve casing and the cylinder of the 1200MW nuclear turbine fc Low cycle fatigue crack propagation life N for warm start fw Thermal start low cycle fatigue crack propagation life N fh Normal shutdown low cycle fatigue crack propagation life N fn The results are given in Table 6 for a pressurized water reactorInlet temperature of nuclear 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 fc Infinite ∞ 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 fc =1890 times
2 Low cycle fatigue from start to stop at warm state N fh =2310 times
3 Low cycle fatigue of hot start and stop N fh =3620 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.
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 CLtoc Calculated according to the following formula:
Figure GDA0003638870840000122
and S705, calculating the total service life of the valve shell of the nuclear turbine and the inner surface of the cylinder.
For example, the total internal life tau of the 1200MW nuclear power CLtic Calculated 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.
For example, the total life tau of the valve shell and the weak life part of the cylinder of the 1200MW nuclear power turbine CLt Calculated according to the following formula:
τ CLtc ＝min{τ CLtoc ,τ CLtic }＝min{τ CLtoc ,τ CLtic ＞τ CLtoc }＝τ CLtoc =75.07 years
And S707, optimally controlling the low-cycle fatigue and creep life of the valve shell and the cylinder of the nuclear turbine.
The optimization control comprises monitoring the total service life of a valve casing and a cylinder of the nuclear turbine, generating a design optimization improvement strategy of the nuclear turbine in response to the condition that the total service life does not meet the qualification requirement, optimizing the valve casing and the cylinder based on the optimization improvement strategy, and executing S701-S707 again until the total service life of the valve casing and the cylinder is more than or equal to 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 designed and controlled:
due to tau CLtc The year of 75.07 is more than 60 years, the design monitoring of the pressure of the service life weak part of the valve casing and the cylinder of the 1200MW nuclear turbine and the low cycle fatigue and creep life of the thermal load 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 1200MW nuclear turbine is in a controlled state, 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 1200MW nuclear turbine is finished, and the process that the rotor, the valve casing and the cylinder bear the action of the rapid starting thermal stress and the service life reaches 60 years can be entered.
The total service life of valve casing and cylinder has been obtained in this disclosed embodiment to optimize valve casing and cylinder when valve casing and cylinder total life do not satisfy the qualified condition of control, made the life of nuclear power steam turbine valve casing and cylinder can reach qualified condition.
Fig. 8 is a flowchart of a multi-dimensional life monitoring method for a nuclear turbine according to an embodiment of the present disclosure, and on the basis of the above embodiment, further referring to fig. 8, a process of life operation monitoring is explained, including the following steps:
s801, acquiring thermal stress monitoring parameters of the rotor, the valve casing and the cylinder which bear rapid starting under multiple working conditions.
Inputting a metal temperature t of a measuring point at a depth of 85-95% of the wall thickness of an inner cylinder based on a component model library server, a load database server and a material database server of a nuclear turbine 95 And the metal temperature t of a measuring point at the depth of 85% -95% of the wall thickness of the valve shell 95v And the metal temperature t of a measuring point at the depth of 85-95% of the wall thickness of the cylinder 95c Measuring point metal temperature t at depth of 45% -50% of wall thickness of valve shell 50v And the metal temperature t of a measuring point at the depth of 45-50% of the wall thickness of the cylinder 50c Design parameters of a rotor, a valve casing and a cylinder of the nuclear turbine, three-dimensional mechanical model and material mechanical property data, a method and a subprogram for monitoring the rapid starting excessive thermal stress borne by the rotor, the valve casing and the cylinder are used for calculating to obtain a rotor pair of the nuclear turbineThermal stress σ for 60 year Life thr The valve shell of the nuclear turbine corresponds to the thermal stress sigma with the service life of 60 years thv Thermal stress sigma corresponding to 60-year service life of nuclear turbine cylinder thc And a simulated value t of the mean temperature of the rotor volume during the starting, stopping or running of the nuclear turbine mi 。
Wherein the calculated sigma thr 、σ thv 、σ thc 、t mi Parameters were monitored for thermal stress.
S802, determining Wen Chabi of the nuclear turbine as third life monitoring data according to the thermal stress monitoring parameters.
And acquiring temperature data of the rotor, the valve shell and the cylinder, and determining Wen Chabi of the nuclear turbine according to the thermal stress monitoring parameters and the temperature data. And the temperature difference ratio of the nuclear turbine is third life monitoring data.
The temperature data of the rotor, the valve casing and the cylinder is t input based on the server in step S701 95 、t 95v 、t 50v 、t 95c 、t 50c And calculated t mi . The volume average temperature difference of the rotor, the valve shell and the cylinder can be calculated according to the temperature data.
Wherein, the mean temperature difference delta t of the rotor volume mr Is calculated as Δ t mr ＝|t mi -t 95 | valve shell product mean temperature difference Δ t mv Is calculated as Δ t mv ＝|t 50v -t 95v Average temperature difference Δ t of cylinder volume mc Is calculated as Δ t mc ＝|t 50c -t 95c |。
The temperature difference ratio of the nuclear turbine rotor, the valve casing and the cylinder can be determined according to the thermal stress monitoring parameters and the volume average temperature difference calculated by the temperature data.
Rotor temperature difference ratio R Δtr Is calculated by the formula
Figure GDA0003638870840000131
Wherein E is the elastic modulus of the rotor material at the working temperature, beta is the linear expansion coefficient of the rotor material at the working temperature,μ is the poisson's ratio of the rotor material at the operating temperature.
Valve casing temperature difference ratio R Δtv Is calculated by the formula
Figure GDA0003638870840000141
Wherein E is the elastic modulus of the valve casing material at the working temperature, beta is the linear expansion coefficient of the valve casing material at the working temperature, and mu is the Poisson's ratio of the valve casing material at the working temperature.
Temperature difference ratio R of cylinder Δtc Is calculated by the formula
Figure GDA0003638870840000142
Wherein E is the elastic modulus of the cylinder material at the working temperature, beta is the linear expansion coefficient of the cylinder material at the working temperature, and mu is the Poisson's ratio of the cylinder material at the working temperature.
The temperature difference ratio of the nuclear turbine is determined by the maximum value among the temperature difference ratios of the rotor, the valve casing and the cylinder, namely R Δtmax ＝{R Δtr ,R Δtv ,R Δtc }。
And S803, responding to the condition that the third life monitoring data do not meet the qualified monitoring conditions, and generating an optimization and improvement strategy of the starting process of the nuclear turbine.
Optionally, the monitoring qualified condition is that the third life monitoring data is smaller than 1, and when the third life monitoring data is larger than or equal to 1, an optimization improvement strategy of the starting process of the nuclear turbine is generated.
Alternatively, the start-up process optimization strategy may include the rate of change of the inlet steam temperature of the nuclear turbine.
S804, optimizing the starting process according to the optimization improvement strategy, continuously monitoring the third life monitoring data, updating the optimization improvement strategy if the newly acquired third life monitoring data still does not meet the monitoring qualified conditions, and continuously optimizing the starting process based on the updated optimization improvement strategy.
And optimizing the starting process according to an optimization and improvement strategy, optionally reducing the change rate of the steam inlet temperature of the nuclear turbine to 0.5-0.8 times of the current change rate, and monitoring the optimized third life monitoring data.
If the third life monitoring data acquired again meets the monitoring qualified conditions, the life operation monitoring is finished; if the newly acquired third life monitoring data still do not meet the monitoring qualified conditions, updating the optimization improvement strategy, and optionally, reducing the change rate of the steam inlet temperature of the nuclear turbine again.
And optimizing the starting process based on the updated optimization and improvement strategy, continuously monitoring the third life monitoring data, updating the optimization and improvement strategy again when the third life monitoring data does not meet the monitoring qualified conditions, and optimizing the starting process until the third life monitoring data meets the monitoring qualified conditions.
In the embodiment of the disclosure, thermal stress monitoring parameters of a rotor, a valve casing and a cylinder which bear rapid starting under multiple working conditions are obtained, wen Chabi of a nuclear turbine is determined according to the thermal stress monitoring parameters to serve as third life monitoring data, an optimization improvement strategy of the starting process of the nuclear turbine is generated in response to the fact that the third life monitoring data do not meet monitoring qualified conditions, the starting process is optimized according to the optimization improvement strategy, the third life monitoring data are monitored continuously, if the newly obtained third life monitoring data do not meet the monitoring qualified conditions, the optimization improvement strategy is updated, and the starting process is optimized continuously based on the updated optimization improvement strategy. In the embodiment of the disclosure, the third life monitoring data is obtained, and the starting process is optimized when the third life monitoring data does not meet the monitoring qualified condition, so that Wen Chabi of the nuclear turbine is reduced, and the service life of the nuclear turbine can reach the qualified condition.
Fig. 9 is a flowchart of a multi-dimensional life monitoring method for a nuclear turbine according to an embodiment of the present disclosure, and as shown in fig. 9, based on the life monitoring method provided by the present disclosure, in an actual application scenario, a process of monitoring an operation of a rotor, a valve casing, and a cylinder, which have a life of 60 years under a rapid-start thermal stress effect, includes the following steps:
and S901, calculating thermal stress monitoring parameters of the rotor, the valve shell and the cylinder which bear the rapid starting thermal stress.
For example, for a certain model 1200MW nuclear power turbine, based on a component model library server 1, a load database server 2 and a material database server 3 of the nuclear power turbine, 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 power turbine, and three-dimensional mechanical model and material mechanical property data, a method for monitoring the excessive thermal stress born 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 model 1200MW nuclear power turbine rotor thr Thermal stress sigma of nuclear turbine valve casing corresponding to 60-year service life of =692MPa thv Thermal stress sigma of 60-year service life corresponding to cylinder of nuclear turbine in a pressure of =458MPa thc =463MPa, and simulated value t of mean temperature of rotor volume in starting, stopping or running process of nuclear turbine mi ＝100℃。
S902, calculating the volume average temperature difference of the nuclear turbine rotor on line.
For example, the metal temperature on-line monitoring value t of the inner cylinder of the 1200MW nuclear power turbine 95 =270 ℃, and the average temperature difference delta t of the volume of the rotor of the 1200MW nuclear power turbine is calculated on line mr Calculated according to the following formula:
Δt mr ＝|t mi -t 95 |＝|100-270|＝170℃
in the above formula, t mi Is a simulated value of the rotor volume mean temperature during the start-up process of 100 DEG C 95 The 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 ℃.
S903, calculating the mean temperature difference of the nuclear turbine valve shell on line.
For example, the model 1200MW nuclear turbine inlet valve casing metal temperature on-line monitoring value t 95 =271 ℃ and t 50 =138 ℃, and the mean temperature difference delta t of the valve shell volume of the 1200MW nuclear power turbine is calculated on line mv Calculated according to the following formula:
Δt mv ＝|t 50v -t 95v |＝|138-271|＝133℃
in the above formula, t 50v The 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 95v The temperature of the metal measured at the position of 85% -95% of the wall thickness of the valve shell is measured, and the temperature of the metal measured at the position of 95% of the wall thickness of the valve shell is measured to be 271 ℃;
and S904, calculating the volume average temperature difference of the cylinder of the nuclear turbine on line.
For example, the model 1200MW nuclear turbine cylinder metal temperature on-line monitoring value t 95 =240 ℃ and t 50 =130 ℃, and the volume average temperature difference delta t of the cylinder of the 1200MW nuclear power turbine is calculated on line mc Calculated according to the following formula:
Δt mc ＝|t 50c -t 95c |＝|130-240|＝110℃
in the above formula, t 50c The temperature of the metal measured at the depth of 45% -50% of the cylinder wall thickness is measured at 130 ℃ t 95c The temperature of the metal at the measuring point at the depth of 85% -95% of the wall thickness of the cylinder is 240 ℃ in the embodiment;
s905, calculating the rotor Wen Chabi of the nuclear turbine on line.
For example, the temperature difference ratio R of the rotor of the 1200MW nuclear turbine Δtr Calculated according to the following formula:
Figure GDA0003638870840000151
in the above formula,. DELTA.t mr The 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 10 5 MPa 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 thr The thermal stress 692MPa corresponding to the 60-year service life of a nuclear turbine rotor;
s906, calculating a valve casing Wen Chabi of the nuclear turbine on line.
For example, the valve casing temperature difference ratio R of the 1200MW nuclear turbine Δtv Calculated according to the following formula:
Figure GDA0003638870840000152
in the above formula,. DELTA.t mv The mean temperature difference of the valve shell is 133 ℃, and E is the elastic modulus of the valve shell material at the working temperature 1.994 multiplied by 10 5 MPa 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 thv The thermal stress of the valve casing of the nuclear turbine is 458MPa corresponding to the 60-year service life;
s907, calculating a nuclear turbine cylinder Wen Chabi on line.
For example, the temperature difference ratio R of the cylinder of the 1200MW nuclear power turbine Δtc Calculated according to the following formula:
Figure GDA0003638870840000161
in the above formula,. DELTA.t mc The 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 10 5 MPa 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 thc The thermal stress of a nuclear turbine cylinder corresponding to the 60-year service life is 463MPa;
s908, determining the maximum temperature difference ratio of the nuclear turbine.
For example, the maximum temperature difference ratio R of the 1200MW nuclear power turbine Δtmax Calculated according to the following formula:
R Δtmax ＝{R Δtr ,R Δtv ,R Δtc }＝{0.885，1.022，0.847}＝1.022
and S909, carrying out life optimization control on the rotor, the valve shell and the cylinder under the action of quick starting thermal stress.
The optimization control comprises monitoring the maximum temperature difference ratio of the nuclear turbine, generating an operation optimization improvement strategy of the nuclear turbine in response to the temperature difference ratio not meeting qualified conditions, optimizing the starting process based on the optimization improvement strategy, and executing steps from S901 to S909 again until the temperature difference ratio is less than 1.
For example, the service life of the rotor, the valve casing and the cylinder of the 1200MW nuclear turbine subjected to the action of rapid starting excessive thermal stress is optimally designed and controlled:
due to R Δtmax The service life of the rotor, the valve casing and the cylinder of the 1200MW nuclear power turbine is unqualified, the starting process of the 1200MW nuclear power turbine needs to be optimized and improved in the operation stage, the change rate of the steam inlet temperature of the 1200MW nuclear power turbine is reduced to 0.6 time of the current temperature, the steps 901 to 908 are executed again, and the monitoring result is listed in 7; at this time R Δtmax If 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
901 Rotor volume average temperature simulation value t mi ＝100℃ t mi ＝103℃
902 Mean temperature difference of rotor volume Δt mr ＝170℃ Δt mr ＝159℃
903 Valve housing volume average temperature difference Δt mv ＝133℃ Δt mv ＝117℃
904 Mean temperature difference of cylinder volume Δt mc ＝110℃ Δt mc ＝102℃
905 Rotor temperature difference ratio R Δtr ＝0.885 R Δtr ＝0.796
906 Valve casing temperature difference ratio R Δtv ＝1.022 R Δtv ＝0.877
907 Temperature difference ratio of cylinder R Δtc ＝0.847 R Δtc ＝0.785
908 Maximum temperature difference ratio of nuclear turbine R Δtmax ＝1.022 R Δtmax ＝0.877
909 Lifetime optimization control Unqualified monitoring of service life The service life is qualified by monitoring
According to the embodiment of the disclosure, the maximum Wen Chabi of the nuclear turbine is obtained, the starting process is optimized when the temperature difference ratio does not meet the monitoring qualified condition, wen Chabi of the nuclear turbine is reduced, and the service life of the nuclear turbine can reach the qualified condition.
On the basis of the above embodiment, a monitoring report of the nuclear turbine may also be printed or output, where the monitoring report may include monitoring data of multiple dimensions under each target of the nuclear turbine and a corresponding optimization and improvement strategy. Optionally, information such as an optimization result of the nuclear turbine can be included.
Fig. 10 is a structural diagram of a multi-dimensional life monitoring apparatus of a nuclear power turbine according to an embodiment of the present disclosure, and as shown in fig. 10, the multi-dimensional life monitoring apparatus 1000 of the nuclear power turbine includes:
the first obtaining module 1010 is used for obtaining 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;
a second obtaining module 1020, configured to obtain second life monitoring data of low cycle fatigue and creep deformation under the multi-operating-condition of the valve casing and the cylinder of the nuclear turbine under the action of pressure and thermal load;
a third obtaining module 1030, configured to obtain third life monitoring data of the nuclear turbine under the multi-condition of the rotor, the valve casing, and the cylinder, where the third life monitoring data is under the action of a rapid starting thermal stress;
a generating module 1040, configured to generate an optimization improvement policy of the nuclear steam turbine according to at least one abnormal life monitoring data of the first life monitoring data, the second life monitoring data, and the third life monitoring data;
and the optimization module 1050 is used for optimizing the nuclear turbine according to an optimization improvement strategy.
In the embodiment of the disclosure, the nuclear turbine is subjected to multi-dimensional design monitoring and operation monitoring to obtain a plurality of life monitoring data, and the nuclear turbine is subjected to design optimization or operation optimization based on abnormal life monitoring data, so that the service life of the nuclear turbine can be effectively prolonged under the action of various damage mechanisms.
It should be noted that the explanation of the foregoing embodiment of the multidimensional service life monitoring method for a nuclear turbine is also applicable to the multidimensional service life monitoring device for a nuclear turbine of this embodiment, and details are not repeated here.
Further, in a possible implementation manner of the embodiment of the present disclosure, the first obtaining module 1010 is further configured to: acquiring first crack initiation life parameters of low cycle fatigue and high cycle fatigue of a rotor; acquiring a first crack propagation life parameter of low cycle fatigue and high cycle fatigue of the rotor; and determining first life monitoring data according to the first crack initiation life parameter and the first crack propagation life parameter.
Further, in a possible implementation manner of the embodiment of the present disclosure, the first obtaining module 1010 is further configured to: and determining a life weak part of the rotor, and acquiring a first crack initiation life parameter and a first crack propagation life parameter of the life weak part of the rotor.
Further, in a possible implementation manner of the embodiment of the present disclosure, the first obtaining module 1010 is further configured to: acquiring first operating state data of the nuclear turbine with a rotor under the action of centrifugal force, thermal load and gravity load under multiple working conditions; determining the total service life of the outer surface of the rotor and the total service life of the inner surface and the inner part of the rotor according to the first operating state data, the first crack initiation service life parameter and the first crack propagation service life parameter; the total life of the rotor is determined based on the total life of the outer surface of the rotor and the total life of the inner surface and the inner portion of the rotor.
Further, in a possible implementation manner of the embodiment of the present disclosure, the second obtaining module 1020 is further configured to: acquiring a second crack initiation life parameter of low cycle fatigue and creep of the valve shell and the cylinder; acquiring a second crack propagation life parameter of low-cycle fatigue and creep of the valve shell and the cylinder; and determining second life monitoring data according to the second crack initiation life parameter and the second crack propagation life parameter.
Further, in a possible implementation manner of the embodiment of the present disclosure, the second obtaining module 1020 is further configured to: and determining the service life weak part of the valve shell and the cylinder, and acquiring a second crack initiation service life parameter and a second crack propagation service life parameter of the service life weak part of the valve shell and the cylinder.
Further, in a possible implementation manner of the embodiment of the present disclosure, the second obtaining module 1020 is further configured to: acquiring second operation state data of the nuclear turbine under the multi-working condition of the valve shell and the cylinder under the action of pressure and heat load; determining the total service life of the outer surface of the valve shell and the cylinder and the total service life of the inner surface of the valve shell and the cylinder according to the second operating state data, the second crack initiation service life parameter and the second crack propagation service life parameter; the total life of the valve housing and the cylinder is determined based on the total life of the valve housing and the outer surface of the cylinder and the total life of the valve housing and the inner surface of the cylinder.
Further, in a possible implementation manner of the embodiment of the present disclosure, the third obtaining module 1030 is further configured to: acquiring thermal stress monitoring parameters of the rotor, the valve shell and the cylinder which bear quick start under multiple working conditions; and determining Wen Chabi of the nuclear turbine as third life monitoring data according to the thermal stress monitoring parameters.
Further, in a possible implementation manner of the embodiment of the present disclosure, the third obtaining module 1030 is further configured to: acquiring temperature data of a rotor, a valve shell and a cylinder; and determining Wen Chabi of the nuclear turbine according to the thermal stress monitoring parameters and the temperature data.
Further, in a possible implementation manner of the embodiment of the present disclosure, the generating module 1040 is further configured to: judging whether the nuclear power turbine meets monitoring qualified conditions or not according to the first service life monitoring data, the second service life monitoring data and the third service life monitoring data; and if one of the life monitoring data does not meet the monitoring qualified condition, generating an optimization improvement strategy of the nuclear turbine based on the abnormal life monitoring data which does not meet the monitoring qualified condition.
Further, in a possible implementation manner of the embodiment of the present disclosure, the generating module 1040 is further configured to: acquiring a part to which abnormal life monitoring data belongs, and calling an optimization model of the nuclear turbine based on the part to which the abnormal life monitoring data belongs; and generating an optimization improvement strategy of the nuclear turbine based on the optimization model.
Further, in a possible implementation manner of the embodiment of the present disclosure, the optimization module 1050 is further configured to: acquiring an adjusting component of the nuclear turbine according to an optimization and improvement strategy; and optimizing the adjusting component according to the adjusting parameters of the adjusting component in the optimization and improvement strategy.
Further, in a possible implementation manner of the embodiment of the present disclosure, the optimization module 1050 is further configured to: and continuing to monitor the abnormal life monitoring data which do not meet the monitoring qualified conditions, if the newly acquired life monitoring data still do not meet the monitoring qualified conditions, updating the optimization improvement strategy, and continuing to optimize the adjusting part based on the updated optimization improvement strategy.
The present disclosure also provides an electronic device, a readable storage medium, and a computer program product according to embodiments of the present disclosure.
FIG. 11 illustrates a schematic block diagram of an example electronic device 110 that can be used to implement embodiments of the present disclosure. Electronic devices are intended to represent various forms of digital computers, such as laptops, desktops, workstations, personal digital assistants, servers, blade servers, mainframes, and other appropriate computers. The electronic device may also represent various forms of mobile devices, such as personal digital processing, cellular phones, smart phones, wearable devices, and other similar computing devices. The components shown herein, their connections and relationships, and their functions, are meant to be examples only, and are not meant to limit implementations of the disclosure described and/or claimed herein.
As shown in fig. 11, the nuclear turbine life monitoring system includes a memory 111, a processor 112 and a computer program stored in the memory 111 and executable on the processor 112, and when the processor 112 executes the program, the foregoing multi-dimensional life monitoring method for the nuclear turbine is implemented.
In the context of this disclosure, a machine-readable medium may be a tangible medium that can contain, or store a program for use by or in connection with an instruction execution system, apparatus, or device. The machine-readable medium may be a machine-readable signal medium or a machine-readable storage medium. A machine-readable medium may include, but is not limited to, an electronic, magnetic, optical, electromagnetic, infrared, or semiconductor system, apparatus, or device, or any suitable combination of the foregoing. More specific examples of a machine-readable storage medium would include an electrical connection based on one or more wires, a portable computer diskette, a hard disk, a Random Access Memory (RAM), a read-only memory (ROM), an erasable programmable read-only memory (EPROM or flash memory), an optical fiber, a compact disc read-only memory (CD-ROM), an optical storage device, a magnetic storage device, or any suitable combination of the foregoing.
To provide for interaction with a user, the systems and techniques described here can be implemented on a computer having: a display device (e.g., a CRT (cathode ray tube) or LCD (liquid crystal display) monitor) for displaying information to a user; and a keyboard and a pointing device (e.g., a mouse or a trackball) by which a user can provide input to the computer. Other kinds of devices may also be used to provide for interaction with a user; for example, feedback provided to the user can be any form of sensory feedback (e.g., visual feedback, auditory feedback, or tactile feedback); and input from the user may be received in any form, including acoustic, speech, or tactile input.
The systems and techniques described here can be implemented in a computing system that includes a back-end component (e.g., as a data server), or that includes a middleware component (e.g., an application server), or that includes a front-end component (e.g., a user computer having a graphical user interface or a web browser through which a user can interact with an implementation of the systems and techniques described here), or any combination of such back-end, middleware, or front-end components. The components of the system can be interconnected by any form or medium of digital data communication (e.g., a communication network). Examples of communication networks include: local Area Networks (LANs), wide Area Networks (WANs), and the Internet.
The computer system may include clients and servers. A client and server are generally remote from each other and typically interact through a communication network. The relationship of client and server arises by virtue of computer programs running on the respective computers and having a client-server relationship to each other. The server may be a cloud server, a server of a distributed system, or a server with a combined blockchain.
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 one or more of that feature. In the description of the present invention, "a plurality" means two or more unless specifically defined otherwise.
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 invention. 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.
Although embodiments of the present invention have been shown and described above, it is understood that the above embodiments are exemplary and should not be construed as limiting the present invention, and that variations, modifications, substitutions and alterations can be made to the above embodiments by those of ordinary skill in the art within the scope of the present invention.

Claims (25)

1. A multi-dimensional service life monitoring method of a nuclear turbine is characterized by comprising the following steps:
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 heat load borne by a valve casing and a cylinder of the nuclear power steam 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;
generating an optimization improvement strategy of the nuclear turbine according to at least one abnormal life monitoring data in the first life monitoring data, the second life monitoring data and the third life monitoring data;
optimizing the nuclear turbine according to the optimization improvement strategy;
obtain the third life-span monitored control data that rotor, valve casing and the cylinder multiplex condition of nuclear power steam turbine bore quick start thermal stress effect down includes:
acquiring thermal stress monitoring parameters of the rotor, the valve shell and the cylinder which bear quick start under multiple working conditions;
determining the temperature difference ratio of the nuclear turbine as the third life monitoring data according to the thermal stress monitoring parameter;
the determining the temperature difference ratio of the nuclear turbine according to the thermal stress monitoring parameters comprises the following steps:
acquiring temperature data of the rotor, the valve shell and the cylinder;
determining the temperature difference ratio of the nuclear turbine according to the thermal stress monitoring parameters and the temperature data;
the step of determining the temperature difference ratio of the nuclear turbine according to the thermal stress monitoring parameters and the temperature data comprises the following steps:
calculating the volume average temperature difference of the rotor, the valve shell and the cylinder according to the thermal stress monitoring parameters and the temperature data;
according to the volume average temperature difference of the rotor, the valve casing and the cylinder, determining the temperature difference ratio of the rotor, the valve casing and the cylinder of the nuclear turbine;
determining the temperature difference ratio of the nuclear turbine according to the temperature difference ratio of the nuclear turbine rotor, the valve casing and the cylinder;
the calculation formula of the rotor temperature difference ratio is as follows:
Figure 170008DEST_PATH_IMAGE001
wherein the content of the first and second substances,R Δtr the ratio of the temperature difference of the rotor is,Eis the modulus of elasticity of the rotor material at the operating temperature,βthe linear expansion coefficient of the rotor material at the operating temperature,µis the Poisson's ratio, Δ t, of the rotor material at the operating temperature mr Is the average temperature difference of the rotor volume,σ thr is that it isMonitoring a thermal stress parameter of the rotor;
wherein, the formula of calculating the valve casing temperature difference ratio is as follows:
Figure 368908DEST_PATH_IMAGE002
wherein the content of the first and second substances,R Δtv in order to obtain the valve housing temperature difference ratio,Ewhich is the modulus of elasticity of the valve housing material at the operating temperature,βas the linear expansion coefficient of the valve housing material at the operating temperature,µpoisson ratio, Δ t, of valve housing material at operating temperature mv The average temperature difference of the valve shell volume is obtained,σ thv monitoring a parameter for thermal stress of the valve housing;
wherein, the calculation formula of the cylinder temperature difference ratio is as follows:
Figure 568946DEST_PATH_IMAGE003
wherein the content of the first and second substances,R Δtc as the ratio of the temperature difference of the cylinder,Eis the modulus of elasticity of the cylinder material at the operating temperature,βwhich is the linear expansion coefficient of the cylinder material at the operating temperature,µis the Poisson's ratio, Δ t, of the cylinder material at the operating temperature mc The average temperature difference of the cylinder volume is obtained,σ thc a parameter is monitored for thermal stress of the cylinder.
2. The method of claim 1, wherein the obtaining first life monitoring data for low cycle fatigue and high cycle fatigue of the rotor of the nuclear turbine subject to centrifugal, thermal, and gravitational loading under a plurality of operating conditions comprises:
acquiring first crack initiation life parameters of low cycle fatigue and high cycle fatigue of the rotor;
acquiring a first crack propagation life parameter of low cycle fatigue and high cycle fatigue of the rotor;
and determining the first life monitoring data according to the first crack initiation life parameter and the first crack propagation life parameter.
3. The method of claim 2, further comprising:
and determining a life weak part of the rotor, and acquiring the first crack initiation life parameter and the first crack propagation life parameter of the life weak part of the rotor.
4. The method of claim 2, wherein determining the first life monitoring data based on the first crack initiation life parameter and the first crack propagation life parameter comprises:
acquiring first operating state data of the nuclear turbine under the action of centrifugal force, thermal load and gravity load borne by the rotor under a plurality of working conditions;
determining the total service life of the outer surface of the rotor and the total service life of the inner surface and the inner part of the rotor according to the first operating state data, the first crack initiation life parameter and the first crack propagation life parameter;
determining the total life of the rotor based on the total life of the outer surface of the rotor and the total life of the inner surface and the inner portion of the rotor.
5. The method of claim 1, wherein the obtaining second life monitoring data for low cycle fatigue and creep under pressure and thermal loading in the valve casing and cylinder of the nuclear turbine includes:
acquiring a second crack initiation life parameter of low cycle fatigue and creep of the valve shell and the cylinder;
acquiring a second crack propagation life parameter of low cycle fatigue and creep of the valve shell and the cylinder;
and determining the second life monitoring data according to the second crack initiation life parameter and the second crack propagation life parameter.
6. The method of claim 5, further comprising:
and determining the service life weak part of the valve shell and the cylinder, and acquiring the second crack initiation life parameter and the second crack propagation life parameter of the service life weak part of the valve shell and the cylinder.
7. The method of claim 5, wherein determining the second life monitoring data from the second crack initiation life parameter and the second crack propagation life parameter comprises:
acquiring second operation state data of the nuclear turbine under the action of pressure and heat load borne by the valve casing and the cylinder under multiple working conditions;
determining a total valve housing to cylinder outer surface life and a total valve housing to cylinder inner surface life based on the second operating condition data, the second crack initiation life parameter, and the second crack propagation life parameter;
determining the total life of the valve housing and the cylinder based on the total life of the outer surface of the valve housing and the cylinder and the total life of the inner surface of the valve housing and the cylinder.
8. The method according to any one of claims 1 to 7, wherein said generating an optimized improvement strategy for said nuclear power turbine based on at least one abnormal life monitoring data of said first, second and third life monitoring data comprises:
judging whether the nuclear turbine meets monitoring qualified conditions or not according to the first service life monitoring data, the second service life monitoring data and the third service life monitoring data;
and if one of the life monitoring data does not meet the monitoring qualified condition, generating an optimization improvement strategy of the nuclear turbine based on the abnormal life monitoring data which does not meet the monitoring qualified condition.
9. The method of claim 8, wherein generating an optimized improvement strategy for the nuclear turbine based on the abnormal life monitoring data that fails to meet the monitored qualifying condition comprises:
acquiring a part to which the abnormal life monitoring data belongs, and calling an optimization model of the nuclear turbine based on the part to which the abnormal life monitoring data belongs;
and generating an optimization improvement strategy of the nuclear turbine based on the optimization model.
10. The method of claim 9, wherein said optimizing said nuclear power turbine according to said optimization improvement strategy comprises:
acquiring an adjusting component of the nuclear turbine according to the optimization and improvement strategy;
and optimizing the adjusting component according to the adjusting parameters of the adjusting component in the optimization improvement strategy.
11. The method of claim 10, wherein after optimizing the tuning component according to the tuning parameters of the tuning component in the optimization improvement strategy, the method further comprises:
and continuing to monitor the abnormal life monitoring data which do not meet the monitoring qualified conditions, if the newly acquired life monitoring data still do not meet the monitoring qualified conditions, updating the optimization improvement strategy, and continuing to optimize the adjusting component based on the updated optimization improvement strategy.
12. A multi-dimensional life monitoring device of a nuclear turbine, comprising:
the system comprises a first acquisition module, a second acquisition module and a third acquisition module, wherein the first acquisition module is used for 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;
the second acquisition module is used for acquiring second life monitoring data of low-cycle fatigue and creep deformation under the action of pressure and heat load borne by a valve shell of the nuclear turbine and a cylinder under multiple working conditions;
the third acquisition module is used for acquiring third life monitoring data of the rotor, the valve casing and the cylinder of the nuclear turbine under the action of quick starting thermal stress under multiple working conditions;
the generating module is used for generating an optimization improvement strategy of the nuclear turbine according to at least one abnormal life monitoring data in the first life monitoring data, the second life monitoring data and the third life monitoring data;
the optimization module is used for optimizing the nuclear turbine according to the optimization improvement strategy;
the third obtaining module is further configured to:
acquiring thermal stress monitoring parameters of the rotor, the valve shell and the cylinder which bear quick start under multiple working conditions;
determining the temperature difference ratio of the nuclear turbine as the third life monitoring data according to the thermal stress monitoring parameter;
the third obtaining module is further configured to:
acquiring temperature data of the rotor, the valve shell and the cylinder;
determining the temperature difference ratio of the nuclear turbine according to the thermal stress monitoring parameters and the temperature data;
the step of determining the temperature difference ratio of the nuclear turbine according to the thermal stress monitoring parameters and the temperature data comprises the following steps:
calculating the volume average temperature difference of the rotor, the valve shell and the cylinder according to the thermal stress monitoring parameters and the temperature data;
determining the temperature difference ratio of the rotor, the valve casing and the cylinder of the nuclear turbine according to the volume average temperature difference of the rotor, the valve casing and the cylinder;
determining the temperature difference ratio of the nuclear turbine according to the temperature difference ratio of the nuclear turbine rotor, the valve casing and the cylinder;
the calculation formula of the rotor temperature difference ratio is as follows:
Figure 562309DEST_PATH_IMAGE001
wherein the content of the first and second substances,R Δtr the rotor temperature difference ratio is E, the elastic modulus of the rotor material at the working temperature is E,βthe linear expansion coefficient of the rotor material at the operating temperature,µis the Poisson's ratio, Δ t, of the rotor material at the operating temperature mr Is the average temperature difference of the rotor volume,σ thr monitoring a parameter for thermal stress of the rotor;
wherein, the formula of calculating valve casing temperature difference ratio is:
Figure 316639DEST_PATH_IMAGE002
wherein the content of the first and second substances,R Δtv in order to obtain the valve housing temperature difference ratio,Ewhich is the modulus of elasticity of the valve housing material at the operating temperature,βas the linear expansion coefficient of the valve housing material at the operating temperature,µpoisson ratio, Δ t, of valve housing material at operating temperature mv The average temperature difference of the valve shell volume is obtained,σ thv monitoring a parameter for thermal stress of the valve housing;
wherein, the calculation formula of the cylinder temperature difference ratio is as follows:
Figure 584809DEST_PATH_IMAGE003
wherein the content of the first and second substances,R Δtc in order to obtain the cylinder temperature difference ratio,Eis the modulus of elasticity of the cylinder material at the operating temperature,βwhich is the linear expansion coefficient of the cylinder material at the operating temperature,µpoisson's ratio, Δ t, for cylinder material at operating temperature mc The average temperature difference of the cylinder volume is obtained,σ thc a parameter is monitored for thermal stress of the cylinder.
13. The apparatus of claim 12, wherein the first obtaining module is further configured to:
acquiring first crack initiation life parameters of low cycle fatigue and high cycle fatigue of the rotor;
acquiring a first crack propagation life parameter of low cycle fatigue and high cycle fatigue of the rotor;
and determining the first life monitoring data according to the first crack initiation life parameter and the first crack propagation life parameter.
14. The apparatus of claim 13, wherein the first obtaining module is further configured to:
and determining a life weak part of the rotor, and acquiring the first crack initiation life parameter and the first crack propagation life parameter of the life weak part of the rotor.
15. The apparatus of claim 13, wherein the first obtaining module is further configured to:
acquiring first operating state data of the nuclear turbine under the action of centrifugal force, thermal load and gravity load borne by the rotor under multiple working conditions;
determining the total service life of the outer surface of the rotor and the total service life of the inner surface and the inner part of the rotor according to the first operating state data, the first crack initiation life parameter and the first crack propagation life parameter;
determining the total life of the rotor based on the total life of the outer surface of the rotor and the total life of the inner surface and the inner portion of the rotor.
16. The apparatus of claim 12, wherein the second obtaining module is further configured to:
acquiring a second crack initiation life parameter of low cycle fatigue and creep of the valve shell and the cylinder;
acquiring a second crack propagation life parameter of low cycle fatigue and creep of the valve shell and the cylinder;
and determining the second life monitoring data according to the second crack initiation life parameter and the second crack propagation life parameter.
17. The apparatus of claim 16, wherein the second obtaining module is further configured to:
and determining the service life weak part of the valve shell and the cylinder, and acquiring the second crack initiation life parameter and the second crack propagation life parameter of the service life weak part of the valve shell and the cylinder.
18. The apparatus of claim 16, wherein the second obtaining module is further configured to:
acquiring second operation state data of the nuclear turbine under the action of pressure and heat load borne by the valve casing and the cylinder under multiple working conditions;
determining the total service life of the outer surface of the valve shell and the cylinder and the total service life of the inner surface of the valve shell and the cylinder according to the second operating state data, the second crack initiation life parameter and the second crack propagation life parameter;
determining the total life of the valve housing and the cylinder based on the total life of the outer surface of the valve housing and the cylinder and the total life of the inner surface of the valve housing and the cylinder.
19. The apparatus according to any one of claims 12-18, wherein the generating module is further configured to:
judging whether the nuclear turbine meets monitoring qualified conditions or not according to the first service life monitoring data, the second service life monitoring data and the third service life monitoring data;
and if one of the life monitoring data does not meet the monitoring qualified condition, generating an optimization improvement strategy of the nuclear turbine based on the abnormal life monitoring data which does not meet the monitoring qualified condition.
20. The apparatus of claim 19, wherein the generating module is further configured to:
acquiring a component to which the abnormal life monitoring data belongs, and calling an optimization model of the nuclear turbine based on the component to which the abnormal life monitoring data belongs;
and generating an optimization improvement strategy of the nuclear turbine based on the optimization model.
21. The apparatus of claim 20, wherein the optimization module is further configured to:
acquiring an adjusting component of the nuclear turbine according to the optimization and improvement strategy;
and optimizing the adjusting component according to the adjusting parameter of the adjusting component in the optimization and improvement strategy.
22. The apparatus of claim 21, wherein the optimization module is further configured to:
and continuing to monitor the abnormal life monitoring data which do not meet the monitoring qualified conditions, if the newly acquired life monitoring data still do not meet the monitoring qualified conditions, updating the optimization improvement strategy, and continuing to optimize the adjusting component based on the updated optimization improvement strategy.
23. An electronic device comprising a memory, a processor;
wherein the processor runs a program corresponding to the executable program code by reading the executable program code stored in the memory for implementing the method according to any one of claims 1 to 11.
24. A computer-readable storage medium, on which a computer program is stored which, when being executed by a processor, carries out the method according to any one of claims 1-11.
25. A computer program product comprising a computer program which, when executed by a processor, implements the method according to any one of claims 1-11.
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