CN116773665A - Cylinder stress corrosion and low cycle fatigue safety monitoring method for nuclear turbine - Google Patents
Cylinder stress corrosion and low cycle fatigue safety monitoring method for nuclear turbine Download PDFInfo
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Abstract
The disclosure provides a cylinder stress corrosion and low cycle fatigue safety monitoring method for a nuclear turbine. The method comprises the following steps: acquiring phased array detection crack depth of a cylinder of a nuclear turbine, and acquiring stress corrosion crack extension life and low cycle fatigue crack extension life of the cylinder under different crack extension categories; detecting crack depth based on a phased array, acquiring crack expansion types of the cylinder, and acquiring crack expansion calendar life of the cylinder based on stress corrosion crack expansion life and low cycle fatigue crack expansion life of the cylinder under the crack expansion types; and based on the crack propagation calendar life, performing crack propagation life safety monitoring on the cylinder. Therefore, the influences of stress corrosion and low cycle fatigue on the service life of the cylinder can be comprehensively considered, so that the safety monitoring of crack propagation service life of the cylinder is carried out, and the long-life safe operation of the cylinder of the nuclear turbine is ensured.
Description
Technical Field
The disclosure relates to the technical field of nuclear turbines, in particular to a cylinder stress corrosion and low cycle fatigue safety monitoring method, device, electronic equipment, storage medium and platform of a nuclear turbine.
Background
At present, along with the aggravation of the problem of energy shortage, people are urgently required to develop new energy to meet the energy demands of people, nuclear power is clean energy, no carbon dioxide is discharged, and the environmental impact is small; nuclear power is a high-efficiency energy source, and has high energy density and low resource consumption; nuclear power is a stable energy source, has no intermittent property, uses long hours and has stable power supply capacity; nuclear power is a safe energy source, the possibility of accident occurrence is small, and the nuclear power is an important option for enhancing energy safety. The nuclear turbine is an important device in nuclear power technology. In the related art, crack extension life safety monitoring is required to be carried out on the nuclear turbine so as to ensure normal operation of the nuclear turbine, however, the problem that stress corrosion is not considered in the crack extension life safety monitoring of the nuclear turbine exists.
Disclosure of Invention
The present disclosure aims to solve, at least to some extent, one of the technical problems in the art described above.
To this end, a first object of the present disclosure is to propose a method for monitoring cylinder stress corrosion and low cycle fatigue safety of a nuclear turbine.
A second object of the present disclosure is to provide a cylinder stress corrosion and low cycle fatigue safety monitoring device for a nuclear turbine.
A third object of the present disclosure is to propose an electronic device.
A fourth object of the present disclosure is to propose a computer readable storage medium.
A fifth object of the present disclosure is to provide a monitoring platform suitable for a nuclear turbine.
An embodiment of a first aspect of the present disclosure provides a method for monitoring cylinder stress corrosion and low cycle fatigue safety of a nuclear turbine, including: acquiring phased array detection crack depth of a cylinder of a nuclear turbine, and acquiring stress corrosion crack extension life and low cycle fatigue crack extension life of the cylinder under different crack extension categories; detecting crack depth based on the phased array, obtaining a crack growth class of the cylinder, and obtaining a crack growth calendar life of the cylinder based on stress corrosion crack growth life and low cycle fatigue crack growth life of the cylinder under the crack growth class; and based on the crack propagation calendar life, performing crack propagation life safety monitoring on the cylinder.
An embodiment of a second aspect of the present disclosure provides a cylinder stress corrosion and low cycle fatigue safety monitoring device for a nuclear turbine, including: the first acquisition module is used for acquiring phased array detection crack depth of a cylinder of the nuclear turbine and acquiring stress corrosion crack extension life and low cycle fatigue crack extension life of the cylinder under different crack extension categories; the second acquisition module is used for detecting crack depth based on the phased array, acquiring crack extension types of the cylinder, and acquiring crack extension calendar life of the cylinder based on stress corrosion crack extension life and low cycle fatigue crack extension life of the cylinder under the crack extension types; and the monitoring module is used for carrying out crack extension service life safety monitoring on the cylinder based on the crack extension calendar service life.
An embodiment of a third aspect of the present disclosure provides an electronic device, including: the system comprises a memory, a processor and a computer program stored on the memory and capable of running on the processor, wherein the processor realizes the cylinder stress corrosion and low cycle fatigue safety monitoring method of the nuclear turbine according to the embodiment of the first aspect of the disclosure when the processor executes the program.
An embodiment of a fourth aspect of the present application provides a computer readable storage medium having a computer program stored thereon, which when executed by a processor, implements a method for monitoring cylinder stress corrosion and low cycle fatigue safety of a nuclear turbine according to an embodiment of the first aspect of the present disclosure.
An embodiment of a fifth aspect of the present application provides a monitoring platform suitable for a nuclear turbine, including a cylinder stress corrosion and low cycle fatigue safety monitoring device of the nuclear turbine according to an embodiment of the second aspect of the present disclosure; or an electronic device as described in embodiments of the third aspect of the present disclosure; or a computer readable storage medium as described in an embodiment of the fourth aspect of the present disclosure.
The technical scheme provided by the embodiment of the disclosure at least brings the following beneficial effects: the method comprises the steps of obtaining phased array detection crack depth of a cylinder of a nuclear turbine, obtaining stress corrosion crack extension life and low cycle fatigue crack extension life of the cylinder under different crack extension categories, obtaining the crack extension category of the cylinder based on the phased array detection crack depth, obtaining crack extension calendar life of the cylinder based on the stress corrosion crack extension life and the low cycle fatigue crack extension life of the cylinder, and carrying out crack extension life safety monitoring on the cylinder based on the crack extension calendar life. Therefore, the influences of stress corrosion and low cycle fatigue on the service life of the cylinder can be comprehensively considered, so that the safety monitoring of crack propagation service life of the cylinder is carried out, and the long-life safe operation of the cylinder of the nuclear turbine is ensured.
It is to be understood that both the foregoing general description and the following detailed description are exemplary and explanatory only and are not restrictive of the disclosure.
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The foregoing and/or additional aspects and advantages of the present disclosure will become apparent and readily appreciated from the following description of the embodiments, taken in conjunction with the accompanying drawings, in which:
FIG. 1 is a flow diagram of a method for monitoring cylinder stress corrosion and low cycle fatigue safety of a nuclear turbine according to one embodiment of the present disclosure;
FIG. 2 is a flow chart of a method for monitoring cylinder stress corrosion and low cycle fatigue safety of a nuclear turbine according to another embodiment of the present disclosure;
FIG. 3 is a schematic flow chart of a method for monitoring cylinder stress corrosion and low cycle fatigue safety of a nuclear turbine to obtain stress corrosion crack growth life in accordance with one embodiment of the present disclosure;
FIG. 4 is a schematic flow chart of a method for monitoring cylinder stress corrosion and low cycle fatigue safety of a nuclear turbine to obtain stress corrosion crack growth life in accordance with another embodiment of the present disclosure;
FIG. 5 is a flow chart of a method for acquiring low cycle fatigue crack growth life in a method for monitoring cylinder stress corrosion and low cycle fatigue safety of a nuclear turbine according to one embodiment of the present disclosure;
FIG. 6 is a flow chart of a method of cylinder stress corrosion and low cycle fatigue safety monitoring for a nuclear turbine according to another embodiment of the present disclosure;
FIG. 7 is a flow chart of a method of cylinder stress corrosion and low cycle fatigue safety monitoring for a nuclear turbine according to another embodiment of the present disclosure;
FIG. 8 is a flow chart of a method of cylinder stress corrosion and low cycle fatigue safety monitoring for a nuclear turbine according to another embodiment of the present disclosure;
FIG. 9 is a schematic structural view of a cylinder stress corrosion and low cycle fatigue safety monitoring device for a nuclear turbine according to one embodiment of the present disclosure;
fig. 10 is a schematic structural view of an electronic device according to an embodiment of the present disclosure.
Detailed Description
Embodiments of the present disclosure are described in detail below, examples of which are illustrated in the accompanying drawings, wherein like or similar reference numerals refer to like or similar elements or elements having like or similar functions throughout. The embodiments described below by referring to the drawings are exemplary and intended for the purpose of explaining the present disclosure and are not to be construed as limiting the present disclosure.
The cylinder stress corrosion and low cycle fatigue safety monitoring method, device, electronic equipment, storage medium and platform of the nuclear turbine according to the embodiment of the disclosure are described below with reference to the accompanying drawings.
FIG. 1 is a flow chart of a method for monitoring cylinder stress corrosion and low cycle fatigue safety of a nuclear turbine according to one embodiment of the present disclosure.
As shown in fig. 1, a cylinder stress corrosion and low cycle fatigue safety monitoring method of a nuclear turbine according to an embodiment of the present disclosure includes:
s101, acquiring phased array detection crack depth of a cylinder of the nuclear turbine, and acquiring stress corrosion crack extension life and low cycle fatigue crack extension life of the cylinder under different crack extension categories.
It should be noted that, the method for monitoring the cylinder stress corrosion and the low cycle fatigue safety of the nuclear turbine according to the embodiments of the present disclosure may be performed by the device for monitoring the cylinder stress corrosion and the low cycle fatigue safety of the nuclear turbine according to the embodiments of the present disclosure, and the device for monitoring the cylinder stress corrosion and the low cycle fatigue safety of the nuclear turbine according to the embodiments of the present disclosure may be configured in any monitoring platform suitable for the nuclear turbine, so as to perform the method for monitoring the cylinder stress corrosion and the low cycle fatigue safety of the nuclear turbine according to the embodiments of the present disclosure.
The phased array detection of the crack depth refers to phased array detection of the cylinder, and the crack depth of the cylinder is obtained. The phased array detection can be implemented by any phased array detection method in the related art.
In one embodiment, obtaining the phased array detection crack depth of the cylinder of the nuclear turbine comprises performing phased array detection on the cylinder through a phased array ultrasonic flaw detector and a phased array probe to obtain the phased array detection crack depth, and if no crack is found in the phased array detection of the cylinder, setting the phased array detection crack depth as a set value. The set value is not limited to a large value, and may be, for example, 0.002m (meter).
For example, in a certain type of the No. 1 low-pressure inner cylinder of the 1000MW nuclear turbine A, the material of the inner cylinder is Q235B, and stress corrosion cracking tends to occur when NaOH is contained in water vapor or seawater leaks from a condenser. The service life weak part of the low-pressure inner cylinder is the connection part of the low-pressure inner cylinder and a second-stage steam extraction pipeline, and the second-stage steam extraction pipeline and the low pressureThe radius of the structural transition fillet at the structural discontinuity of the connecting part of the inner cylinder is 20mm. This location operates near the transition between superheated steam and wet steam, the saturated steam line (Wilson), and is prone to stress corrosion cracking. In the manufacturing stage of the nuclear turbine A, carrying out phased array nondestructive testing on a No. 1 low-pressure inner cylinder of the nuclear turbine A, and giving the crack depth a of the connecting part of the No. 1 low-pressure inner cylinder of the nuclear turbine A and a second-stage steam extraction pipeline under the condition that no crack is found in the phased array nondestructive testing i ＝2mm＝0.002m。
For example, a number 2 low-pressure inner cylinder of a certain type 1000MW nuclear turbine B has a material Q235B, and has a tendency of stress corrosion cracking when NaOH is contained in water vapor or seawater leaks from a condenser. The service life weak part of the low-pressure inner cylinder is the connection part of the low-pressure inner cylinder and the second-stage steam extraction pipeline, and the radius of a structural transition fillet at the structural discontinuity part of the connection part of the second-stage steam extraction pipeline and the low-pressure inner cylinder is 20mm. This location operates near the transition between superheated steam and wet steam, the saturated steam line (Wilson), and is prone to stress corrosion cracking. In the manufacturing stage of the nuclear turbine B, carrying out phased array nondestructive testing on a No. 2 low-pressure inner cylinder of the nuclear turbine B to obtain the crack depth a of the connecting part of the No. 2 low-pressure inner cylinder and the second-stage steam extraction pipeline of the nuclear turbine B i ＝5mm＝0.005m。
For example, a certain type of 1000MW nuclear turbine C operates for 20 years, and phased array nondestructive testing and crack propagation life safety monitoring are carried out on a No. 1 low-pressure inner cylinder of the nuclear turbine C in planned overhaul. The low-pressure inner cylinder material is Q235B, and stress corrosion cracking tends to occur when NaOH is contained in water vapor or seawater leaks from a condenser. The service life weak part of the low-pressure inner cylinder is the connection part of the low-pressure inner cylinder and the second-stage steam extraction pipeline, and the radius of a structural transition fillet at the structural discontinuity part of the connection part of the second-stage steam extraction pipeline and the low-pressure inner cylinder is 20mm. This location operates near the transition between superheated steam and wet steam, the saturated steam line (Wilson), and is prone to stress corrosion cracking. In the using stage of the nuclear turbine C, phased array nondestructive testing is carried out on a No. 1 low-pressure inner cylinder of the nuclear turbine C to obtain a No. 1 low-pressure inner cylinder of the nuclear turbine C Crack depth a of connection part of cylinder and second-stage steam extraction pipeline i ＝5mm＝0.005m。
For example, a certain type of 1000MW nuclear turbine D is operated for 20 years, and phased array nondestructive testing and crack propagation life safety monitoring are carried out on a No. 2 low-pressure inner cylinder of the nuclear turbine D in planned overhaul. The low-pressure inner cylinder material is Q235B, and stress corrosion cracking tends to occur when NaOH is contained in water vapor or seawater leaks from a condenser. The service life weak part of the No. 2 low-pressure inner cylinder of the nuclear power steam turbine D is the connection part of the low-pressure inner cylinder and the second-stage steam extraction pipeline, and the radius of a structural transition fillet at the structural discontinuity part of the connection part of the second-stage steam extraction pipeline and the low-pressure inner cylinder is 20mm. This location operates near the transition between superheated steam and wet steam, the saturated steam line (Wilson), and is prone to stress corrosion cracking. In the using stage of the nuclear turbine D, phased array nondestructive testing is carried out on a No. 2 low-pressure inner cylinder of the nuclear turbine D to obtain the crack depth a of the connecting part of the No. 2 low-pressure inner cylinder and the second-stage steam extraction pipeline of the nuclear turbine D i ＝10mm＝0.010m。
The stress corrosion crack growth life refers to the crack growth life of the cylinder when the type of damage to which the cylinder is subjected includes stress corrosion, and the low cycle fatigue crack growth life refers to the crack growth life of the cylinder when the type of damage to which the cylinder is subjected includes low cycle fatigue.
It should be noted that, the acquisition of the stress corrosion crack growth life and the low cycle fatigue crack growth life of the cylinder can be achieved by using related technologies, and are not limited in this regard.
In one embodiment, obtaining stress corrosion crack growth life and low cycle fatigue crack growth life of the cylinder under different crack growth categories includes determining life base data matching a target crack growth life, crack growth category, and obtaining the target crack growth life under the crack growth category based on the life base data. Wherein the target crack growth life is any one of stress corrosion crack growth life and low cycle fatigue crack growth life.
The life basic data may include, for example, a crack growth size set, stress calculation basic data of the cylinder, material test basic data, and the like.
S102, detecting crack depth based on a phased array, obtaining crack extension types of the cylinder, and obtaining the crack extension calendar life of the cylinder based on stress corrosion crack extension life and low cycle fatigue crack extension life of the cylinder under the crack extension types.
In one embodiment, the method comprises the steps of obtaining a crack propagation category of the cylinder based on the phased array detection crack depth, wherein the method comprises the steps of obtaining a set interval in which the phased array detection crack depth is located, and obtaining the crack propagation category of the cylinder based on a mapping relation between the set interval and the crack propagation category. It is understood that a plurality of setting intervals may be divided in advance for the phased array inspection crack depth, and different setting intervals may map different crack propagation categories, or may map the same crack propagation category.
For example, based on the phased array detection crack depth, a crack propagation class of the cylinder is obtained, including determining the first crack propagation class as the crack propagation class of the cylinder if the phased array detection crack depth is in a first set interval, or determining the second crack propagation class as the crack propagation class of the cylinder if the phased array detection crack depth is in a second set interval.
In one embodiment, the crack growth calendar life of the cylinder is obtained based on the stress corrosion crack growth life and the low cycle fatigue crack growth life of the cylinder under the crack growth category, including inputting the stress corrosion crack growth life and the low cycle fatigue crack growth life of the cylinder under the crack growth category into a set model, and outputting the crack growth calendar life from the set model. It should be noted that the setting model is not limited too much, and for example, a deep learning model may be included.
In one embodiment, the crack propagation calendar life of the cylinder is obtained based on the stress corrosion crack propagation life and the low cycle fatigue crack propagation life of the cylinder under the crack propagation category, the calendar life of each stage of the cylinder is obtained based on the stress corrosion crack propagation life and the low cycle fatigue crack propagation life of the cylinder, and the sum of the calendar lives of each stage of the cylinder is determined as the crack propagation calendar life of the cylinder. It should be noted that the stages refer to crack propagation stages of the cylinder, the number of stages is plural, and different phased array detection crack depths and different crack propagation size sets of the cylinder may correspond to different categories and different stages.
And S103, performing crack extension life safety monitoring on the cylinder based on the crack extension calendar life.
In one embodiment, the safety monitoring of the crack propagation life of the cylinder is performed based on the crack propagation calendar life, including obtaining a monitoring criterion value of the cylinder, determining that the cylinder is not subject to safety abnormality if the crack propagation calendar life is greater than or equal to the monitoring criterion value, and determining that the cylinder is subject to safety abnormality if the crack propagation calendar life is less than the monitoring criterion value.
In some examples, after determining that the cylinder is experiencing the security anomaly, generating indication information for indicating that the cylinder is experiencing the security anomaly is further included to inform a user in time that the cylinder is experiencing the security anomaly.
In some examples, a mapping relationship between the model of the cylinder and the monitoring criterion value may be pre-established, the monitoring criterion value of the cylinder may be obtained, including querying the monitoring criterion value in the mapping relationship based on the model of the cylinder, and determining the queried monitoring criterion value as the monitoring criterion value of the cylinder.
In summary, according to the method for monitoring cylinder stress corrosion and low cycle fatigue safety of a nuclear turbine of the embodiment of the present disclosure, a phased array detection crack depth of a cylinder of the nuclear turbine is obtained, a stress corrosion crack growth life and a low cycle fatigue crack growth life of the cylinder under different crack growth categories are obtained, the crack growth category of the cylinder is obtained based on the phased array detection crack depth, the stress corrosion crack growth life and the low cycle fatigue crack growth life under the crack growth category of the cylinder are obtained, a crack growth calendar life of the cylinder is obtained, and the crack growth life safety monitoring is performed on the cylinder based on the crack growth calendar life. Therefore, the influences of stress corrosion and low cycle fatigue on the service life of the cylinder can be comprehensively considered, so that the safety monitoring of crack propagation service life of the cylinder is carried out, and the long-life safe operation of the cylinder of the nuclear turbine is ensured.
FIG. 2 is a flow chart of a method for cylinder stress corrosion and low cycle fatigue safety monitoring of a nuclear turbine according to another embodiment of the present disclosure.
As shown in fig. 2, a cylinder stress corrosion and low cycle fatigue safety monitoring method of a nuclear turbine according to an embodiment of the present disclosure includes:
s201, acquiring phased array detection crack depth of a cylinder of the nuclear turbine, and acquiring stress corrosion crack extension life and low cycle fatigue crack extension life of the cylinder under different crack extension categories.
For the relevant content of step S201, refer to the above embodiment, and will not be described herein.
S202, acquiring a crack extension size set of the cylinder.
It should be noted that the set of crack growth sizes is not excessively limited, and may include, for example, a stress corrosion crack growth size threshold value a SCC Low cycle fatigue critical crack size a of cylinder in cold starting transient working condition of nuclear turbine cc Low cycle fatigue critical crack size a of cylinder in nuclear turbine temperature state starting transient working condition cw Low cycle fatigue critical crack size a of cylinder in nuclear turbine thermal state starting transient state working condition ch Etc.
In one embodiment, obtaining a set of crack growth sizes for the cylinder includes obtaining stress calculation basis data for the cylinder, obtaining material test basis data for the cylinder, and determining the set of crack growth sizes based on the stress calculation basis data and the material test basis data. Thus, the method can comprehensively consider stress calculation basic data and material experiment basic data to determine a crack propagation size set.
The stress calculation basic data and the material test basic data are not excessively limited.
For example, the stress calculation basic data comprises cylinder crack parts of the load operation steady-state working condition of the nuclear turbineMaximum stress sigma of bit max0 Cylinder crack part maximum stress sigma of cold starting transient working condition of nuclear turbine maxc Maximum stress sigma of crack part of cylinder under transient state working condition of nuclear turbine temperature state starting maxw Maximum stress sigma of crack part of cylinder under thermal starting transient working condition of nuclear turbine maxh Etc.
For example, the material test base data includes the fracture toughness K of the cylinder material IC Fracture toughness K of cylinder material under stress corrosion ISCC Annual average stress corrosion crack growth rate test valueCrack shape parameter Q, etc.
In some examples, the set of crack propagation dimensions is determined based on stress calculation basis data and material experiment basis data, including the following several possible implementations:
mode 1, determining a stress corrosion crack propagation size threshold value of a cylinder based on a crack shape parameter of the cylinder, stress corrosion fracture toughness of a cylinder material and maximum stress of a crack part of the cylinder under load operation steady-state working condition of a nuclear turbine.
Mode 2, determining the low cycle fatigue critical crack size of the cylinder under the cold starting transient working condition of the nuclear turbine based on the crack shape parameter of the cylinder, the fracture toughness of the cylinder material and the maximum stress of the crack part of the cylinder under the cold starting transient working condition of the nuclear turbine.
And 3, determining the low cycle fatigue critical crack size of the cylinder under the condition of the nuclear turbine temperature starting transient state based on the crack shape parameter of the cylinder, the fracture toughness of the cylinder material and the maximum stress of the crack part of the cylinder under the condition of the nuclear turbine temperature starting transient state.
And 4, determining the low cycle fatigue critical crack size of the cylinder in the thermal starting transient working condition of the nuclear turbine based on the crack shape parameter of the cylinder, the fracture toughness of the cylinder material and the maximum stress of the crack part of the cylinder in the thermal starting transient working condition of the nuclear turbine.
For example, taking the low-pressure inner cylinder No. 1 of the nuclear turbine a as an example, stress calculation base data and material test base data of the low-pressure inner cylinder No. 1 of the nuclear turbine a are shown in tables 1 and 2, respectively.
TABLE 1 stress calculation basis data for Low pressure inner cylinders
| Sequence number | Project | Data value |
| 1 | Maximum stress sigma of crack part of cylinder under steady-state working condition of load operation max0 /MPa | 229.120 |
| 2 | Maximum stress sigma at crack position of cylinder under cold starting transient working condition maxc /MPa | 252.970 |
| 3 | Maximum stress sigma of crack part of cylinder under temperature state starting transient working condition maxw /MPa | 267.093 |
| 4 | Maximum stress sigma of crack part of cylinder under thermal state starting transient working condition maxh /MPa | 237.736 |
TABLE 2 Material test basis data for Low pressure inner cylinders
The crack propagation size set of the No. 1 low-pressure inner cylinder of the nuclear turbine A is calculated as follows:
for example, taking the No. 2 low-pressure inner cylinder of the nuclear turbine B as an example, stress calculation basic data and material test basic data of the No. 2 low-pressure inner cylinder of the nuclear turbine B are shown in tables 1 and 2, respectively.
The crack propagation size set of the No. 2 low-pressure inner cylinder of the nuclear turbine B is calculated as follows:
for example, taking the low-pressure inner cylinder No. 1 of the nuclear turbine C as an example, stress calculation basic data and material test basic data of the low-pressure inner cylinder No. 1 of the nuclear turbine C are shown in tables 1 and 2, respectively.
The crack propagation size set of the No. 1 low-pressure inner cylinder of the nuclear turbine C is calculated as follows:
for example, taking the No. 2 low-pressure inner cylinder of the nuclear turbine D as an example, the stress calculation base data and the material test base data of the No. 2 low-pressure inner cylinder of the nuclear turbine D are shown in tables 1 and 2, respectively.
The crack propagation size set of the No. 2 low-pressure inner cylinder of the nuclear turbine D is calculated as follows:
s203, detecting crack depth and crack extension size set based on the phased array, and obtaining the crack extension type of the cylinder.
In one embodiment, the method comprises the steps of obtaining a crack extension class of a cylinder based on a phased array detection crack depth and a crack extension size set, and obtaining a crack extension class based on a corresponding relation between the operation result and the crack extension class by performing operation processing on the crack extension size in the phased array detection crack depth and the crack extension size set to obtain the operation result. The operation processing may be implemented by at least one operation processing method in the related art, which is not limited herein, and may include addition, subtraction, multiplication, division, and the like.
In one embodiment, the method further includes obtaining a crack propagation category for the cylinder based on the phased array detection crack depth and the set of crack propagation dimensions, including determining the crack propagation category based on a magnitude relationship between the phased array detection crack depth and crack propagation dimensions in the set of crack propagation dimensions.
In some examples, the crack propagation class of the cylinder is obtained based on the phased array detection crack depth and the set of crack propagation dimensions, including the following several possible implementations:
in the mode 1, if the detected crack depth of the phased array is smaller than the stress corrosion crack propagation size threshold value, determining the crack propagation type as the first crack propagation type.
In some examples, if the crack propagation category is a first crack propagation category, and the first crack propagation category includes two stages, wherein the crack size of the cylinder at the first stage detects the crack depth a from the phased array i To the stress corrosion crack propagation size threshold value a SCC At the second stageCrack size from stress corrosion crack propagation size threshold value a for cylinder under segment SCC To a low cycle fatigue critical crack size a cj . Wherein, the critical crack size a of low cycle fatigue cj Is a as cc Or a cw Or a ch 。
And 2, if the detected crack depth of the phased array is larger than the stress corrosion crack growth size threshold value, determining that the crack growth type is a second crack growth type.
In some examples, if the crack propagation category is a second crack propagation category, and the second crack propagation category includes a stage in which the crack size of the cylinder detects the crack depth a from the phased array at the first stage i To a low cycle fatigue critical crack size a cj 。
For example, continuing with the example of the low pressure inner cylinder No. 1 of the nuclear turbine a in the above embodiment, the stress corrosion crack size threshold value a SCC For 0.008624m, phased array nondestructive testing crack depth a i 0.002m due to a i ＝0.002m<a SCC The crack propagation category of the No. 1 low-pressure inner cylinder of the nuclear turbine a is the first crack propagation category= 0.008624 m.
For example, continuing with the example of the No. 2 low-pressure inner cylinder of the nuclear turbine B in the above embodiment, the stress corrosion crack size threshold value a SCC For 0.008624m, phased array nondestructive testing crack depth a i 0.005m due to a i ＝0.005m<a SCC The crack growth category of the No. 2 low pressure inner cylinder of the nuclear turbine B is the first crack growth category= 0.008624 m.
For example, continuing with the example of the low pressure inner cylinder No. 1 of the nuclear turbine C in the above embodiment, the stress corrosion crack size threshold value a SCC For 0.008624m, phased array nondestructive testing crack depth a i 0.005m due to a i ＝0.005m<a SCC The crack growth category of the No. 1 low pressure inner cylinder of the nuclear turbine C is the first crack growth category= 0.008624 m.
For example, continuing with the example of the low pressure inner cylinder No. 2 of the nuclear turbine D in the above embodiment, the stress corrosion crack size threshold value a SCC For 0.008624m, phased array nondestructive testing crack depth a i 0.010m due to a i ＝0.010m>a SCC The crack growth category of the No. 2 low-pressure inner cylinder of the nuclear turbine D is the second crack growth category= 0.008624 m.
S204, the crack propagation calendar life of the cylinder is obtained based on the stress corrosion crack propagation life and the low cycle fatigue crack propagation life of the cylinder under the crack propagation category.
S205, performing crack extension life safety monitoring on the cylinder based on the crack extension calendar life.
For the relevant content of steps S204-S205, refer to the above embodiment, and are not repeated here.
In summary, according to the method for monitoring the cylinder stress corrosion and low cycle fatigue safety of the nuclear turbine, a crack growth size set of the cylinder is obtained, and crack growth categories of the cylinder are obtained based on the phased array detection of the crack depth and the crack growth size set. Thus, the crack propagation type of the cylinder can be obtained by comprehensively considering the phased array detection crack depth and the crack propagation size set of the cylinder.
On the basis of any of the above embodiments, as shown in fig. 3, obtaining the stress corrosion crack growth life under the first crack growth category includes:
s301, obtaining a first stress corrosion crack extension life under a first crack extension category based on a stress corrosion crack extension size threshold value, a cylinder material annual average stress corrosion crack extension rate test value and a low cycle fatigue critical crack size of a cylinder under a cold starting transient working condition of a nuclear turbine.
In one embodiment, the first stress corrosion crack growth life N under the first crack growth category fSCC1,1 The calculation process of (2) is as follows:
s302, obtaining a second stress corrosion crack extension life under a first crack extension category based on a stress corrosion crack extension size threshold value, a cylinder material annual average stress corrosion crack extension rate test value and a low cycle fatigue critical crack size of a cylinder under a nuclear turbine temperature starting transient working condition.
In one embodiment, the first stress corrosion crack growth life N under the first crack growth category fSCC1,2 The calculation process of (2) is as follows:
s303, obtaining a third stress corrosion crack extension life under the first crack extension category based on a stress corrosion crack extension size threshold value, a cylinder material annual average stress corrosion crack extension rate test value and a low cycle fatigue critical crack size of a cylinder under a nuclear turbine thermal state starting transient state working condition.
In one embodiment, a third stress corrosion crack growth life N under the first crack growth category fSCC1,3 The calculation process of (2) is as follows:
s304, determining the stress corrosion crack growth life under the first crack growth category based on the first stress corrosion crack growth life under the first crack growth category, the second stress corrosion crack growth life under the first crack growth category, and the third stress corrosion crack growth life under the first crack growth category.
In one embodiment, determining the stress corrosion crack growth life under the first crack growth category based on the first stress corrosion crack growth life under the first crack growth category, the second stress corrosion crack growth life under the first crack growth category, and the third stress corrosion crack growth life under the first crack growth category includes weighted averaging the first stress corrosion crack growth life under the first crack growth category, the second stress corrosion crack growth life under the first crack growth category, and the third stress corrosion crack growth life under the first crack growth category to obtain the stress corrosion crack growth life under the first crack growth category.
In one embodiment, determining the stress corrosion crack growth life under the first crack growth category based on a first stress corrosion crack growth life under the first crack growth category, a second stress corrosion crack growth life under the first crack growth category, and a third stress corrosion crack growth life under the first crack growth category includes determining the minimum of the first stress corrosion crack growth life under the first crack growth category, the second stress corrosion crack growth life under the first crack growth category, and the third stress corrosion crack growth life under the first crack growth category as the stress corrosion crack growth life under the first crack growth category.
For example, stress corrosion crack growth life N under the first crack growth category fSCC01 The calculation process of (2) is as follows:
N fSCC01 ＝min{N fSCC1,1 ,N fSCC1,2 ,N fSCC1,3 }
for example, continuing to take the low-pressure inner cylinder No. 1 of the nuclear turbine a in the above embodiment as an example, the crack growth type of the low-pressure inner cylinder No. 1 of the nuclear turbine a is the first crack growth type, and the stress corrosion crack growth life N under the first crack growth type of the low-pressure inner cylinder No. 1 of the nuclear turbine a fSCC01 The calculation process of (2) is as follows:
N fSCC01 ＝min{N fSCC1,1 ,N fSCC1,2 ,N fSCC1,3 } = min {22.741,19.832,26.477} = 19.832 years
For example, continuing to take the number 2 low-pressure inner cylinder of the nuclear turbine B as an example in the above embodiment, the crack growth type of the number 2 low-pressure inner cylinder of the nuclear turbine B is the first crack growth type, and the stress corrosion crack growth life N of the number 2 low-pressure inner cylinder of the nuclear turbine B is the first crack growth type fSCC01 The calculation process of (2) is as follows:
N fSCC01 ＝min{N fSCC1,1 ,N fSCC1,2 ,N fSCC1,3 } = min {22.741,19.832,26.477} = 19.832 years
For example, continuing to take the 1 st low-pressure inner cylinder of the nuclear turbine C as an example in the above embodiment, the crack growth type of the 1 st low-pressure inner cylinder of the nuclear turbine C is the first crack growth type, and the stress corrosion crack growth life N of the 1 st low-pressure inner cylinder of the nuclear turbine C is the first crack growth type fSCC01 The calculation process of (2) is as follows:
N fSCC01 ＝min{N fSCC1,1 ,N fSCC1,2 ,N fSCC1,3 } = min {22.741,19.832,26.477} = 19.832 years
Therefore, the method can comprehensively consider the stress corrosion crack growth size threshold value, the annual average stress corrosion crack growth rate test value of the cylinder material and the low cycle fatigue critical crack size to obtain the first to third stress corrosion crack growth lives under the first crack growth category, and further determine the stress corrosion crack growth life under the first crack growth category.
On the basis of any of the above embodiments, as shown in fig. 4, obtaining the stress corrosion crack growth life under the second crack growth category includes:
s401, obtaining the first stress corrosion crack extension service life under the second crack extension category based on the phased array detection crack depth, the annual average stress corrosion crack extension rate test value of the cylinder material and the low cycle fatigue critical crack size of the cylinder under the cold starting transient working condition of the nuclear turbine.
In one embodiment, the first stress corrosion crack growth life N under the second crack growth category fSCC2,1 The calculation process of (2) is as follows:
s402, obtaining a second stress corrosion crack extension life under a second crack extension category based on the phased array detection crack depth, the annual average stress corrosion crack extension rate test value of the cylinder material and the low cycle fatigue critical crack size of the cylinder under the temperature starting transient working condition of the nuclear turbine.
In one embodiment, the second stress corrosion crack growth life N under the second crack growth category fSCC2,2 The calculation process of (2) is as follows:
s403, obtaining a third stress corrosion crack extension life under a second crack extension category based on the phased array detection crack depth, the annual average stress corrosion crack extension rate test value of the cylinder material and the low cycle fatigue critical crack size of the cylinder under the thermal starting transient working condition of the nuclear turbine.
In one embodiment, a third stress corrosion crack growth life N under the second crack growth category fSCC2,3 The calculation process of (2) is as follows:
s403, determining the stress corrosion crack growth life under the second crack growth category based on the first stress corrosion crack growth life under the second crack growth category, the second stress corrosion crack growth life under the second crack growth category and the third stress corrosion crack growth life under the second crack growth category.
In one embodiment, determining the stress corrosion crack growth life under the second crack growth category based on the first stress corrosion crack growth life under the second crack growth category, the second stress corrosion crack growth life under the second crack growth category, and the third stress corrosion crack growth life under the second crack growth category includes weighted averaging the first stress corrosion crack growth life under the second crack growth category, the second stress corrosion crack growth life under the second crack growth category, and the third stress corrosion crack growth life under the second crack growth category to obtain the stress corrosion crack growth life under the second crack growth category.
In one embodiment, determining the stress corrosion crack growth life under the second crack growth category based on the first stress corrosion crack growth life under the second crack growth category, the second stress corrosion crack growth life under the second crack growth category, and the third stress corrosion crack growth life under the second crack growth category includes determining the minimum of the first stress corrosion crack growth life under the second crack growth category, the second stress corrosion crack growth life under the second crack growth category, and the third stress corrosion crack growth life under the second crack growth category as the stress corrosion crack growth life under the second crack growth category.
For example, stress corrosion crack growth life N under the second crack growth category fSCC02 The calculation process of (2) is as follows:
N fSCC02 ＝min{N fSCC2,1 ,N fSCC2,2 ,N fSCC2,3 }
for example, continuing to take the number 2 low-pressure inner cylinder of the nuclear turbine D as an example in the above embodiment, the crack growth type of the number 2 low-pressure inner cylinder of the nuclear turbine D is the second crack growth type, and the stress corrosion crack growth life N of the number 2 low-pressure inner cylinder of the nuclear turbine D is the second crack growth type fSCC02 The calculation process of (2) is as follows:
/>
N fSCC02 ＝min{N fSCC2,1 ,N fSCC2,2 ,N fSCC2,3 } = min {21.583,18.675,25.319} = 18.675 years
Therefore, the method can comprehensively consider the phased array detection crack depth, the annual average stress corrosion crack growth rate test value of the cylinder material and the low cycle fatigue critical crack size to obtain the first to third stress corrosion crack growth lives under the second crack growth category, and further determine the stress corrosion crack growth life under the second crack growth category.
On the basis of any of the above embodiments, as shown in fig. 5, obtaining low cycle fatigue crack growth life under different crack growth categories includes:
s501, obtaining the low cycle fatigue crack growth life of the first stage of the first crack growth class of the cold start transient state working condition of the nuclear turbine.
In one embodiment, obtaining the low cycle fatigue crack growth life of the first stage of the first crack growth class of the cold start transient condition of the nuclear turbine comprises detecting crack depth, stress corrosion crack growth size threshold value, crack shape parameters of a cylinder, low cycle fatigue crack growth test constants of cylinder materials, and maximum stress of a crack part of the cylinder of the cold start transient condition of the nuclear turbine based on a phased array to obtain the low cycle fatigue crack growth life of the first stage of the first crack growth class of the cold start transient condition of the nuclear turbine.
In some examples, the low cycle fatigue crack growth life N of the first stage of the first crack growth class for cold start transient conditions of the nuclear turbine fc1,1 The calculation process of (2) is as follows:
wherein C is 0 、m 0 Low cycle fatigue crack propagation test constant for the cylinder-averaged material.
S502, obtaining the low cycle fatigue crack growth life of the second stage of the first crack growth type of the cold start transient state working condition of the nuclear turbine.
In one embodiment, the low cycle fatigue crack growth life of the first crack growth class second stage of the cold starting transient operating condition of the nuclear turbine is obtained, wherein the low cycle fatigue crack growth life of the first crack growth class second stage of the cold starting transient operating condition of the nuclear turbine is obtained based on a stress corrosion crack growth size threshold value, a low cycle fatigue critical crack size of a cylinder of the cold starting transient operating condition of the nuclear turbine, a crack shape parameter of the cylinder, a low cycle fatigue crack growth test constant of a cylinder material and a maximum stress of a crack part of the cylinder of the cold starting transient operating condition of the nuclear turbine.
In some examples, the low cycle fatigue crack growth life N of the second stage of the first crack growth class for cold start transient conditions of the nuclear turbine fc1,2 The calculation process of (2) is as follows:
/>
s503, obtaining the low cycle fatigue crack growth life of the first stage of the second crack growth class of the cold start transient state working condition of the nuclear turbine.
In one embodiment, the low cycle fatigue crack growth life of the first stage of the second crack growth class of the cold start transient condition of the nuclear turbine is obtained, wherein the low cycle fatigue crack growth life of the first stage of the second crack growth class of the cold start transient condition of the nuclear turbine is obtained based on the phased array detection crack depth, the low cycle fatigue critical crack size of the cylinder of the cold start transient condition of the nuclear turbine, the crack shape parameter of the cylinder, the low cycle fatigue crack growth test constant of the cylinder material and the maximum stress of the crack part of the cylinder of the cold start transient condition of the nuclear turbine.
In some examples, the low cycle fatigue crack growth life N of the first stage of the second crack growth category for cold start transient conditions of the nuclear turbine fc2,1 The calculation process of (2) is as follows:
s504, obtaining the low cycle fatigue crack growth life of the first stage of the first crack growth class of the temperature start transient state working condition of the nuclear turbine.
In one embodiment, obtaining the low cycle fatigue crack growth life of the first stage of the first crack growth class of the nuclear turbine warm start transient condition comprises detecting crack depth, stress corrosion crack growth size threshold value, crack shape parameters of a cylinder, a cylinder material low cycle fatigue crack growth test constant, and maximum stress of a cylinder crack part of the nuclear turbine warm start transient condition based on a phased array, and obtaining the low cycle fatigue crack growth life of the first stage of the first crack growth class of the nuclear turbine warm start transient condition.
In some examples, the low cycle fatigue crack growth life N of the first stage of the first crack growth class of the warm start transient operating condition of the nuclear turbine fw1,1 The calculation process of (2) is as follows:
s505, obtaining the low cycle fatigue crack growth life of the second stage of the first crack growth type of the temperature start transient state working condition of the nuclear turbine.
In one embodiment, the low cycle fatigue crack growth life of the first crack growth class second stage of the nuclear turbine warm start transient condition is obtained, wherein the low cycle fatigue crack growth life of the first crack growth class second stage of the nuclear turbine warm start transient condition is obtained based on a stress corrosion crack growth size threshold value, a low cycle fatigue critical crack size of a cylinder of the nuclear turbine warm start transient condition, a crack shape parameter of the cylinder, a cylinder material low cycle fatigue crack growth test constant and a maximum stress of a cylinder crack part of the nuclear turbine warm start transient condition.
In some examples, the low cycle fatigue crack growth life N of the second stage of the first crack growth class of the warm start transient operating condition of the nuclear turbine fw1,2 The calculation process of (2) is as follows:
/>
s506, obtaining the low cycle fatigue crack growth life of the first stage of the second crack growth class of the temperature start transient state working condition of the nuclear turbine.
In one embodiment, the low cycle fatigue crack growth life of the first stage of the second crack growth class of the warm-start transient condition of the nuclear turbine is obtained, wherein the low cycle fatigue crack growth life of the first stage of the second crack growth class of the warm-start transient condition of the nuclear turbine is obtained based on the phased array detection crack depth, the low cycle fatigue critical crack size of the cylinder of the warm-start transient condition of the nuclear turbine, the crack shape parameter of the cylinder, the low cycle fatigue crack growth test constant of the cylinder material and the maximum stress of the crack part of the cylinder of the warm-start transient condition of the nuclear turbine.
In some examples, the low cycle fatigue crack growth life N of the first stage of the second crack growth class of the warm start transient condition of the nuclear turbine fw2,1 The calculation process of (2) is as follows:
s507, obtaining the low cycle fatigue crack growth life of the first stage of the first crack growth class of the thermal starting transient working condition of the nuclear turbine.
In one embodiment, obtaining the low cycle fatigue crack growth life of the first stage of the first crack growth class of the thermal start transient condition of the nuclear turbine comprises detecting crack depth, stress corrosion crack growth size threshold value, crack shape parameters of a cylinder, low cycle fatigue crack growth test constants of cylinder materials, and maximum stress of a crack part of the cylinder of the thermal start transient condition of the nuclear turbine based on a phased array to obtain the low cycle fatigue crack growth life of the first stage of the first crack growth class of the thermal start transient condition of the nuclear turbine.
In some examples, the low cycle fatigue crack growth life N of the first stage of the first crack growth class of the hot start transient condition of the nuclear turbine fh1,1 The calculation process of (2) is as follows:
s508, obtaining the low cycle fatigue crack growth life of the second stage of the first crack growth type of the thermal starting transient working condition of the nuclear turbine.
In one embodiment, the low cycle fatigue crack growth life of the first crack growth class second stage of the thermal starting transient operating condition of the nuclear turbine is obtained, wherein the low cycle fatigue crack growth life of the first crack growth class second stage of the thermal starting transient operating condition of the nuclear turbine is obtained based on a stress corrosion crack growth size threshold value, a low cycle fatigue critical crack size of a cylinder of the thermal starting transient operating condition of the nuclear turbine, a crack shape parameter of the cylinder, a low cycle fatigue crack growth test constant of a cylinder material and a maximum stress of a crack part of the cylinder of the thermal starting transient operating condition of the nuclear turbine.
In some examples, the low cycle fatigue crack growth life N of the second stage of the first crack growth category of the hot start transient condition of the nuclear turbine fh1,2 The calculation process of (2) is as follows:
/>
s509, obtaining the low cycle fatigue crack growth life of the first stage of the second crack growth class of the thermal starting transient working condition of the nuclear turbine.
In one embodiment, the low cycle fatigue crack growth life of the first stage of the second crack growth class of the thermal starting transient operating condition of the nuclear turbine is obtained, wherein the low cycle fatigue crack growth life of the first stage of the second crack growth class of the thermal starting transient operating condition of the nuclear turbine is obtained based on the phased array detection crack depth, the low cycle fatigue critical crack size of a cylinder of the thermal starting transient operating condition of the nuclear turbine, the crack shape parameter of the cylinder, the low cycle fatigue crack growth test constant of a cylinder material and the maximum stress of a crack part of the cylinder of the thermal starting transient operating condition of the nuclear turbine.
In some examples, the nuclear turbine heatsSecond crack growth class of state-start transient conditions low cycle fatigue crack growth life N in first stage fh2,1 The calculation process of (2) is as follows:
for example, continuing to take the low-pressure inner cylinder No. 1 of the nuclear turbine a as an example in the above embodiment, the crack propagation type of the low-pressure inner cylinder No. 1 of the nuclear turbine a is the first crack propagation type, and the cylinder crack position life calculation base data of the cold start transient process, the cylinder crack position life calculation base data of the warm start transient process, and the cylinder crack position life calculation base data of the warm start transient process of the low-pressure inner cylinder of the nuclear turbine a are shown in tables 3, 4, and 5, respectively.
Table 3 cylinder crack location life calculation basis data for cold start transients
| Sequence number | Project | Data value |
| 1 | Maximum stress sigma at crack position of cylinder under cold starting transient working condition maxc /MPa | 252.970 |
| 2 | Low cycle fatigue crack growth test constant m for cylinder material 0 | 3.15 |
| 3 | Low cycle fatigue crack growth test constant C for cylinder materials 0 | 4.2×10 -12 |
| 4 | Crack shape parameter Q | 0.88 |
Table 4 cylinder crack location life calculation basis data for temperature start transients
| Sequence number | Project | Data value |
| 1 | Maximum stress sigma of crack part of cylinder under temperature state starting transient working condition maxw /MPa | 267.093 |
| 2 | Low cycle fatigue crack growth test constant m for cylinder material 0 | 3.15 |
| 3 | Low cycle fatigue crack growth test constant C for cylinder materials 0 | 4.2×10 -12 |
Table 5 cylinder crack location life calculation basis data for hot start transients
| Sequence number | Project | Data value |
| 1 | Maximum stress sigma of crack part of cylinder under temperature state starting transient working condition maxh /MPa | 237.736 |
| 2 | Low cycle fatigue crack growth test constant m for cylinder material 0 | 3.15 |
| 3 | Low cycle fatigue crack growth test constant C for cylinder materials 0 | 4.2×10 -12 |
The low cycle fatigue crack growth life of the No. 1 low pressure inner cylinder of the nuclear turbine A is calculated as follows:
/>
for example, continuing to take the example of the No. 2 low-pressure inner cylinder of the nuclear turbine B in the above embodiment, the crack propagation type of the No. 2 low-pressure inner cylinder of the nuclear turbine B is the first crack propagation type, and the cylinder crack position life calculation base data of the cold starting transient process, the cylinder crack position life calculation base data of the warm starting transient process and the cylinder crack position life calculation base data of the warm starting transient process of the No. 2 low-pressure inner cylinder of the nuclear turbine B are shown in tables 3, 4 and 5, respectively.
The low cycle fatigue crack growth life of the No. 2 low pressure inner cylinder of the nuclear turbine B under the first crack growth category is calculated as follows:
/>
for example, continuing to take the example of the No. 1 low-pressure inner cylinder of the nuclear turbine C in the above embodiment, the crack propagation type of the No. 1 low-pressure inner cylinder of the nuclear turbine C is the first crack propagation type, and the cylinder crack position life calculation base data of the cold starting transient process, the cylinder crack position life calculation base data of the warm starting transient process, and the cylinder crack position life calculation base data of the warm starting transient process of the No. 1 low-pressure inner cylinder of the nuclear turbine C are shown in tables 3, 4, and 5, respectively.
The low cycle fatigue crack growth life under the first crack growth category of the No. 1 low pressure inner cylinder of the nuclear turbine C is calculated as follows:
/>
for example, continuing to take the example of the No. 2 low-pressure inner cylinder of the nuclear turbine D in the above embodiment, the crack propagation type of the No. 2 low-pressure inner cylinder of the nuclear turbine D is the second crack propagation type, and the cylinder crack position life calculation base data of the cold starting transient process, the cylinder crack position life calculation base data of the warm starting transient process, and the cylinder crack position life calculation base data of the warm starting transient process of the No. 2 low-pressure inner cylinder of the nuclear turbine D are shown in tables 3, 4, and 5, respectively.
The low cycle fatigue crack growth life under the second crack growth category of the No. 2 low pressure inner cylinder of the nuclear turbine D is calculated as follows:
therefore, the method can comprehensively consider the crack shape parameters of the cylinder, the low cycle fatigue crack growth test constant of the cylinder material, the maximum stress of the crack part of the cylinder and the crack growth size set of the cylinder to obtain the low cycle fatigue crack growth life under different crack growth categories.
FIG. 6 is a flow chart of a method for cylinder stress corrosion and low cycle fatigue safety monitoring of a nuclear turbine according to another embodiment of the present disclosure.
As shown in fig. 6, a cylinder stress corrosion and low cycle fatigue safety monitoring method of a nuclear turbine according to an embodiment of the present disclosure includes:
s601, acquiring phased array detection crack depth of a cylinder of the nuclear turbine, and acquiring stress corrosion crack extension life and low cycle fatigue crack extension life of the cylinder under different crack extension categories.
S602, detecting crack depth based on the phased array, and acquiring crack propagation types of the cylinder.
For the relevant content of steps S601-S602, reference may be made to the above embodiments, and details are not repeated here.
S603, the crack propagation calendar life is obtained based on the stress corrosion crack propagation life and the multi-stage low cycle fatigue crack propagation life of the cylinder under the crack propagation category.
In one embodiment, the crack propagation calendar life is derived based on the stress corrosion crack propagation life and the multi-stage low cycle fatigue crack propagation life under the crack propagation category of the cylinder, including deriving a calendar life for each stage based on the stress corrosion crack propagation life and the multi-stage low cycle fatigue crack propagation life under the crack propagation category of the cylinder, and deriving a crack propagation calendar life based on the calendar life for each stage.
In one embodiment, the crack propagation calendar life is derived based on stress corrosion crack propagation life and multi-stage low cycle fatigue crack propagation life under the crack propagation category of the cylinder, including two possible embodiments:
in embodiment 1, if the crack growth type of the cylinder is the first crack growth type, the crack growth calendar life in the first crack growth type is obtained based on the stress corrosion crack growth life in the first crack growth type and the multi-stage low cycle fatigue crack growth life.
In some examples, the method further comprises obtaining a calendar life of the first stage of the first crack growth category based on a low cycle fatigue crack growth life of the first stage of the first crack growth category of the cold start transient condition of the nuclear turbine, a low cycle fatigue crack growth life of the first stage of the first crack growth category of the warm start transient condition of the nuclear turbine, an annual cold start number, an annual average temperature start number, and an annual average temperature start number of the nuclear turbine.
In some examples, the method further comprises obtaining a calendar life of the first crack growth category second stage based on the stress corrosion crack growth life under the first crack growth category, the low cycle fatigue crack growth life of the first crack growth category second stage of the cold start transient condition of the nuclear turbine, the low cycle fatigue crack growth life of the first crack growth category second stage of the warm start transient condition of the nuclear turbine, the number of times of annual cold starts, the number of times of annual warm starts, and the number of times of annual warm starts of the nuclear turbine.
In some examples, further comprising deriving the crack propagation calendar life under the first crack propagation category based on the calendar life of the first stage of the first crack propagation category, the calendar life of the second stage of the first crack propagation category.
In some examples, the crack propagation calendar life τ under the first crack propagation category CL1 The calculation process of (2) is as follows:
τ CL1 ＝τ CL1,1 +τ CL1,2
wherein τ CL1,1 Calendar life, τ, for the first stage of the first crack propagation category CL1,2 Calendar life, y for the second stage of the first crack propagation category c Is the annual cold state starting times, y of the nuclear turbine w The number of times of annual average temperature state starting of the nuclear turbine, y h The number of times of annual average hot state starting of the nuclear turbine.
For example, continuing to take the example of the No. 1 low-pressure inner cylinder of the nuclear turbine a in the above embodiment, the crack growth type of the No. 1 low-pressure inner cylinder of the nuclear turbine a is the first crack growth type, and the calendar design monitoring basic data of the No. 1 low-pressure inner cylinder of the nuclear turbine a is shown in table 6.
TABLE 6 calendar design monitoring base data for Low pressure inner cylinders
| Sequence number | Project | Data value |
| 1 | Number of times y of annual cold state start c /times | 4 |
| 2 | Number of times y of annual average temperature state start w /times | 20 |
| 3 | Number of times y of annual average hot state start h /times | 75 |
| 4 | Crack growth life safety monitoring criterion value tau 0 Year/year | 60 |
Crack propagation calendar life tau under first crack propagation category of No. 1 low-pressure inner cylinder of nuclear turbine A CL1 The calculation process of (2) is as follows:
for example, continuing to take the number 2 low-pressure inner cylinder of the nuclear turbine B as an example in the above embodiment, the crack growth type of the number 2 low-pressure inner cylinder of the nuclear turbine B is the first crack growth type, and the calendar design monitoring basic data of the number 2 low-pressure inner cylinder of the nuclear turbine B is shown in table 6.
Crack propagation calendar life tau under first crack propagation category of No. 2 low-pressure inner cylinder of nuclear turbine B CL1 The calculation process of (2) is as follows:
for example, continuing to take the example of the No. 1 low-pressure inner cylinder of the nuclear turbine C in the above embodiment, the crack propagation type of the No. 1 low-pressure inner cylinder of the nuclear turbine C is the first crack propagation type, and the calendar design monitoring basic data of the No. 1 low-pressure inner cylinder of the nuclear turbine C is shown in table 7.
TABLE 7 calendar design monitoring base data for Low pressure inner cylinders
| Sequence number | Project | Data value |
| 1 | Number of times y of annual cold state start c /times | 4 |
| 2 | Number of times y of annual average temperature state start w /times | 20 |
| 3 | Number of times y of annual average hot state start h /times | 75 |
| 4 | Planned overhaul interval tau of nuclear turbine m Year/year | 10 |
Crack propagation calendar life tau under first crack propagation category of No. 1 low-pressure inner cylinder of nuclear turbine C CL1 The calculation process of (2) is as follows:
mode 2, if the crack growth type of the cylinder is the second crack growth type, obtaining a crack growth calendar life in the second crack growth type based on the stress corrosion crack growth life in the second crack growth type and the multi-stage low cycle fatigue crack growth life.
In some examples, the calendar life of the first stage of the second crack growth class is obtained based on the stress corrosion crack growth life under the second crack growth class, the low cycle fatigue crack growth life of the first stage of the second crack growth class of the cold start transient condition of the nuclear turbine, the low cycle fatigue crack growth life of the first stage of the second crack growth class of the warm start transient condition of the nuclear turbine, the number of times of annual cold starts, the number of times of annual warm starts, and the number of times of annual warm starts of the nuclear turbine.
In some examples, further comprising deriving the crack propagation calendar life based on the calendar life of the first stage of the second crack propagation category.
In some examples, the crack propagation calendar life τ under the second crack propagation category CL2 The calculation process of (2) is as follows:
wherein τ CL2,1 Calendar life for the first stage of the second crack propagation category.
For example, continuing to take the number 2 low-pressure inner cylinder of the nuclear turbine D as an example in the above embodiment, the crack propagation type of the number 2 low-pressure inner cylinder of the nuclear turbine D is the second crack propagation type, and the calendar design monitoring basic data of the number 2 low-pressure inner cylinder of the nuclear turbine D is shown in table 7.
Crack propagation calendar life tau under second crack propagation category of No. 2 low-pressure inner cylinder of nuclear turbine D CL2 The calculation process of (2) is as follows:
s604, performing crack extension service life safety monitoring on the cylinder based on the crack extension calendar service life.
For the relevant content of step S604, refer to the above embodiment, and will not be described herein.
In summary, according to the method for monitoring the cylinder stress corrosion and low cycle fatigue safety of the nuclear turbine, the annual average cold state starting times, the annual average temperature state starting times and the annual average temperature state starting times of the nuclear turbine, the stress corrosion crack growth life under the crack growth category of the cylinder and the multi-stage low cycle fatigue crack growth life can be comprehensively considered to obtain the crack growth calendar life of the cylinder.
FIG. 7 is a flow chart of a method for cylinder stress corrosion and low cycle fatigue safety monitoring of a nuclear turbine according to another embodiment of the present disclosure.
As shown in fig. 7, a cylinder stress corrosion and low cycle fatigue safety monitoring method of a nuclear turbine according to an embodiment of the present disclosure includes:
s701, acquiring phased array detection crack depth of a cylinder of the nuclear turbine, and acquiring stress corrosion crack extension life and low cycle fatigue crack extension life of the cylinder under different crack extension categories.
S702, detecting crack depth based on a phased array, obtaining crack extension types of the cylinder, and obtaining the crack extension calendar life of the cylinder based on stress corrosion crack extension life and low cycle fatigue crack extension life of the cylinder under the crack extension types.
For the relevant content of steps S701-S702, refer to the above embodiments, and are not repeated here.
S703, if the nuclear turbine is in a manufacturing stage, obtaining a safety coefficient based on the crack propagation calendar life and the crack propagation life safety monitoring criterion value of the cylinder.
S704, judging whether the safety coefficient meets the first monitoring qualification condition.
In one embodiment, the safety factor is derived based on crack propagation calendar life and a crack propagation life safety monitor criterion value for the cylinder, including determining a ratio or a difference of the crack propagation calendar life and the crack propagation life safety monitor criterion value as the safety factor.
In one embodiment, the safety factor is positively correlated with the crack growth calendar life and negatively correlated with the crack growth life safety monitoring criterion value.
It should be noted that, the first condition for monitoring is not limited too much, for example, the safety coefficient may be greater than the first set threshold value, and may be determined as the first condition for monitoring. The first set threshold is not limited too much, and may be 1, for example.
For example, continuing to take the low-pressure inner cylinder No. 1 of the nuclear turbine a as an example in the above embodiment, the crack growth type of the low-pressure inner cylinder No. 1 of the nuclear turbine a is the first crack growth type, the crack growth life safety monitoring criterion values of the low-pressure inner cylinder No. 1 of the nuclear turbine a are shown in table 6, and the crack growth calendar life τ of the low-pressure inner cylinder No. 1 of the nuclear turbine a is in the first crack growth type CL1 For 138.69 years, τ 0 Security coefficient S for 60 years F The calculation process of (2) is as follows:
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the safety coefficient S of the No. 1 low-pressure inner cylinder of the nuclear turbine A can be known F ＝2.31>1, judging the safety coefficient S F The first monitoring qualification condition is satisfied.
For example, continuing to take the number 2 low-pressure inner cylinder of the nuclear turbine B as an example in the above embodiment, the crack growth type of the number 2 low-pressure inner cylinder of the nuclear turbine B is the first crack growth type, the crack growth life safety monitoring criterion values of the number 2 low-pressure inner cylinder of the nuclear turbine B are shown in table 6, and the crack growth calendar life τ of the number 2 low-pressure inner cylinder of the nuclear turbine B is determined under the first crack growth type CL1 For 47.83 years, τ 0 Security coefficient S for 60 years F The calculation process of (2) is as follows:
the safety coefficient S of the No. 2 low-pressure inner cylinder of the nuclear turbine B can be known F ＝0.79<1, judging the safety coefficient S F The first monitor eligibility condition is not satisfied.
S705, if the safety coefficient does not meet the first monitoring qualification condition, acquiring abnormal data of the cylinder in the manufacturing stage.
S706, optimizing and improving the abnormal data of the cylinder in the manufacturing stage, and returning to execute the process of acquiring the safety coefficient until the acquired safety coefficient meets the first monitoring qualification condition.
The abnormal data of the cylinder at the manufacturing stage is not excessively limited, and may include, for example, manufacturing process parameters of the cylinder, stress calculation base data of the cylinder at the manufacturing stage, material test base data of the nuclear turbine at the manufacturing stage, and the like.
In one embodiment, the optimization and improvement of the abnormal data of the cylinder in the manufacturing stage comprises turning or polishing cracks of the cylinder of the nuclear turbine; on the premise of not influencing the structural strength of the cylinder of the nuclear turbine, turning is performed to increase the radius of the fillet at the position where the cylinder of the nuclear turbine is located; partial repair welding; adopting a local heat treatment process to eliminate welding residual stress; finishing and polishing repair welding parts; the machining precision is improved, and the machining stress concentration is eliminated; performing phased array nondestructive monitoring again to determine the crack depth of the cylinder; cylinder shot peening, improved fatigue performance, and the like.
For example, continuing to take the number 2 low-pressure inner cylinder of the nuclear turbine B in the above embodiment as an example, the safety factor S F The method comprises the steps that the first monitoring qualification condition is not met, abnormal data of a manufacturing stage of a No. 2 low-pressure inner cylinder of the nuclear turbine B can be optimized and improved, for example, partial optimization and improvement strategy combination of turning or polishing cracks of the nuclear turbine B, partial repair welding, and partial heat treatment technology to eliminate welding residual stress and finish machining and polishing of repair welding parts is adopted, phased array nondestructive testing is carried out on the optimized No. 2 low-pressure inner cylinder of the nuclear turbine B again, no cracks are found, and under the condition that no cracks are found in the phased array nondestructive testing, the crack depth a of the connecting part of the No. 2 low-pressure inner cylinder of the nuclear turbine B and a second-stage steam extraction pipeline is given i ＝2mm＝0.002m。
Performing crack safety monitoring under the combined action of stress corrosion cracking and low-cycle fatigue damage again, and recalculating the crack extension calendar life of the No. 2 low-pressure inner cylinder of the nuclear turbine B, wherein if the recalculated crack extension calendar life is the crack extension calendar life tau under the first crack extension category CL1 For 138.69 years, τ 0 Security coefficient S for 60 years F The calculation process of (2) is as follows:
The safety coefficient S of the No. 2 low-pressure inner cylinder of the nuclear turbine B can be known F ＝2.31>1, judging the safety coefficient S F And (5) meeting the first monitoring qualification condition, and ending the crack growth life safety monitoring of the No. 2 low-pressure inner cylinder of the nuclear turbine B.
In summary, according to the method for monitoring the safety of the stress corrosion and the low cycle fatigue of the cylinder of the nuclear turbine, if the nuclear turbine is in the manufacturing stage, based on the safety monitoring criterion values of the crack propagation calendar life and the crack propagation life of the cylinder, a safety coefficient is obtained, whether the safety coefficient meets the first monitoring qualification condition is judged, if the safety coefficient does not meet the first monitoring qualification condition, abnormal data of the cylinder in the manufacturing stage is obtained, the abnormal data of the cylinder in the manufacturing stage is optimized and improved, and the process of obtaining the safety coefficient is executed again until the obtained safety coefficient meets the first monitoring qualification condition, so that the safety of the cylinder in the manufacturing stage is improved, and the method is suitable for monitoring the cylinder in the manufacturing stage of the nuclear turbine.
FIG. 8 is a flow chart of a method for cylinder stress corrosion and low cycle fatigue safety monitoring of a nuclear turbine according to another embodiment of the present disclosure.
As shown in fig. 8, a cylinder stress corrosion and low cycle fatigue safety monitoring method of a nuclear turbine according to an embodiment of the present disclosure includes:
s801, obtaining phased array detection crack depth of a cylinder of the nuclear turbine, and obtaining stress corrosion crack extension life and low cycle fatigue crack extension life of the cylinder under different crack extension categories.
S802, detecting crack depth based on a phased array, obtaining crack extension types of the cylinder, and obtaining the crack extension calendar life of the cylinder based on stress corrosion crack extension life and low cycle fatigue crack extension life of the cylinder under the crack extension types.
For the relevant content of steps S801 to S802, refer to the above embodiment, and are not repeated here.
S803, if the nuclear turbine is in a use stage, obtaining a safe multiplying power based on the crack propagation calendar life and the planned overhaul interval of the nuclear turbine.
S804, judging whether the safety multiplying power meets the second monitoring qualification condition.
In one embodiment, the safe magnification is obtained based on the crack propagation calendar life and the planned overhaul interval of the nuclear turbine, including determining a ratio or a difference of the crack propagation calendar life and the planned overhaul interval as the safe magnification.
In one embodiment, the safety factor is positively correlated with the crack propagation calendar life and negatively correlated with the planned overhaul interval.
It should be noted that, the second condition for monitoring is not limited too much, for example, the safety multiplying power may be greater than the second set threshold, and may be determined as the second condition for monitoring. The second set threshold is not excessively limited, and may be 2, for example.
For example, continuing to take the 1 st low-pressure inner cylinder of the nuclear turbine C as an example in the above embodiment, the crack growth type of the 1 st low-pressure inner cylinder of the nuclear turbine C is the first crack growth type, the planned overhaul interval of the nuclear turbine C is shown in table 7, and the crack growth calendar life τ of the 1 st low-pressure inner cylinder of the nuclear turbine C is as follows CL1 For 47.83 years, τ m Security magnification S after 10 years = R The calculation process of (2) is as follows:
safe multiplying power S of No. 1 low-pressure inner cylinder of nuclear turbine C R ＝4.78>2, judging the safety multiplying power S R The second monitoring qualification condition is satisfied.
For example, continuing to take the number 2 low-pressure inner cylinder of the nuclear turbine D as an example in the above embodiment, the crack growth type of the number 2 low-pressure inner cylinder of the nuclear turbine D is the second crack growth type, and the nuclear turbine The planned overhaul interval of D is shown in Table 7, and the crack propagation calendar life τ of the second crack propagation category of the No. 2 low-pressure inner cylinder of the nuclear turbine D CL2 13.65 years, τ m Security magnification S after 10 years = R The calculation process of (2) is as follows:
safe multiplying power S of No. 2 low-pressure inner cylinder of nuclear turbine D R ＝1.37<2, judging the safety multiplying power S R The second monitor eligibility condition is not satisfied.
S805, if the safety multiplying power does not meet the second monitoring qualification condition, acquiring abnormal data of the cylinder in the using stage.
S806, optimizing and improving the abnormal data of the cylinder in the using stage, and returning to the process of acquiring the safety multiplying power until the acquired safety multiplying power meets the second monitoring qualification condition.
The abnormal data of the cylinder in the use stage is not excessively limited, and may include, for example, a use process parameter of the cylinder, stress calculation basic data of the cylinder in the use stage, material test basic data of the nuclear turbine in the use stage, and the like.
In one embodiment, the optimization and improvement of the abnormal data of the cylinder in the using stage comprises turning or polishing cracks of the cylinder of the nuclear turbine; on the premise of not influencing the structural strength of the cylinder of the nuclear turbine, turning is performed to increase the radius of the fillet at the position where the cylinder of the nuclear turbine is located; partial repair welding; adopting a local heat treatment process to eliminate welding residual stress; finishing and polishing repair welding parts; the machining precision is improved, and the machining stress concentration is eliminated; performing phased array nondestructive monitoring again to determine the crack depth of the cylinder; the cylinder is shot-blasted, so that the fatigue performance is improved; optimizing a cold starting parameter change curve of the nuclear turbine, and reducing the thermal stress of a cylinder under a cold starting transient working condition; optimizing a temperature starting parameter change curve of the nuclear turbine, and reducing the thermal stress of a cylinder under a temperature starting transient working condition; optimizing a thermal starting parameter change curve of the nuclear turbine, and reducing thermal stress of a cylinder under a thermal starting transient working condition; adding reinforced water technical supervision to ensure that the quality of the condensed water meets the requirements; the condenser tube bundle is timely plugged after leakage, so that circulating water is prevented from leaking into condensation water in a large amount.
For example, continuing to take the number 2 low-pressure inner cylinder of the nuclear turbine D in the above embodiment as an example, the safety multiplying power S R The abnormal data of the using stage of the No. 2 low-pressure inner cylinder of the nuclear turbine D can be optimized and improved without meeting the second monitoring qualification condition, for example, the crack of the No. 2 low-pressure inner cylinder of the nuclear turbine D is turned or polished, the local repair welding is adopted, the local heat treatment process is adopted, the welding residual stress is eliminated, the repair welding part is finished and polished, the machining precision is improved, the optimization and improvement strategy combination of the machining stress concentration part is eliminated, the phased array nondestructive testing is carried out on the No. 2 low-pressure inner cylinder of the optimized and improved nuclear turbine D again, no crack is found, and under the condition that the phased array nondestructive testing does not find the crack, the crack depth a of the connecting part of the No. 2 low-pressure inner cylinder of the nuclear turbine D and the second-stage steam extraction pipeline is given i ＝2mm＝0.002m。
Performing crack safety monitoring under the combined action of stress corrosion cracking and low-cycle fatigue damage again, and recalculating the crack extension calendar life of the No. 2 low-pressure inner cylinder of the nuclear turbine D, wherein if the recalculated crack extension calendar life is the crack extension calendar life tau under the first crack extension category CL1 For 138.69 years, τ m Security magnification S after 10 years = R The calculation process of (2) is as follows:
safe multiplying power S of No. 2 low-pressure inner cylinder of nuclear turbine D R ＝13.87>2, judging the safety multiplying power S R And (5) meeting the second monitoring qualification condition, and ending the crack extension life safety monitoring of the No. 2 low-pressure inner cylinder of the nuclear turbine D.
In summary, according to the method for monitoring the cylinder stress corrosion and low cycle fatigue safety of the nuclear turbine according to the embodiment of the disclosure, if the nuclear turbine is in the use stage, based on the crack propagation calendar service life and the planned overhaul interval of the nuclear turbine, the safety multiplying power is obtained, whether the safety multiplying power meets the second monitoring qualification condition is judged, if the safety multiplying power does not meet the second monitoring qualification condition, abnormal data of the cylinder in the use stage is obtained, the abnormal data of the cylinder in the use stage is optimized and improved, and the process of obtaining the safety multiplying power is executed again until the obtained safety multiplying power meets the second monitoring qualification condition, so that the safety of the cylinder in the use stage is improved, and the method is suitable for monitoring the cylinder in the use stage of the nuclear turbine.
In order to achieve the above embodiment, the present disclosure further provides a cylinder stress corrosion and low cycle fatigue safety monitoring device for a nuclear turbine.
FIG. 9 is a schematic structural view of a cylinder stress corrosion and low cycle fatigue safety monitoring device for a nuclear turbine according to one embodiment of the present disclosure.
As shown in fig. 9, a cylinder stress corrosion and low cycle fatigue safety monitoring apparatus 100 of a nuclear turbine according to an embodiment of the present disclosure includes: a first acquisition module 110, a second acquisition module 120, and a monitoring module 130.
A first obtaining module 110, configured to obtain a phased array detection crack depth of a cylinder of a nuclear turbine, and obtain a stress corrosion crack growth life and a low cycle fatigue crack growth life of the cylinder under different crack growth categories;
a second obtaining module 120, configured to detect a crack depth based on the phased array, obtain a crack growth class of the cylinder, and obtain a crack growth calendar life of the cylinder based on a stress corrosion crack growth life and a low cycle fatigue crack growth life of the cylinder under the crack growth class;
and the monitoring module 130 is used for performing crack extension service life safety monitoring on the cylinder based on the crack extension calendar service life.
In one embodiment of the present disclosure, the first obtaining module 110 is further configured to: the phased array ultrasonic flaw detector and the phased array probe are used for carrying out phased array detection on the cylinder to obtain the phased array detection crack depth; and if no crack is found in the phased array detection of the cylinder, setting the depth of the phased array detection crack as a set value.
In one embodiment of the present disclosure, the second obtaining module 120 is further configured to: acquiring a crack extension size set of the cylinder; and acquiring the crack propagation category of the cylinder based on the phased array detection crack depth and the crack propagation size set.
In one embodiment of the present disclosure, the second obtaining module 120 is further configured to: acquiring stress calculation basic data of the cylinder; acquiring material test basic data of the cylinder; the set of crack growth dimensions is determined based on the stress calculation basis data and the material experiment basis data.
In one embodiment of the present disclosure, the second obtaining module 120 is further configured to:
determining a stress corrosion crack propagation size threshold value of the cylinder based on the crack shape parameter of the cylinder, the stress corrosion fracture toughness of a cylinder material and the maximum stress of a crack part of the cylinder under load running steady-state working condition of the nuclear turbine;
determining the low cycle fatigue critical crack size of the cylinder in the cold starting transient working condition of the nuclear turbine based on the crack shape parameter of the cylinder, the fracture toughness of the cylinder material and the maximum stress of the crack part of the cylinder in the cold starting transient working condition of the nuclear turbine;
Determining the low cycle fatigue critical crack size of the cylinder of the nuclear turbine temperature starting transient working condition based on the crack shape parameter of the cylinder, the fracture toughness of the cylinder material and the maximum stress of the crack part of the cylinder of the nuclear turbine temperature starting transient working condition;
and determining the low cycle fatigue critical crack size of the cylinder in the thermal starting transient working condition of the nuclear turbine based on the crack shape parameter of the cylinder, the fracture toughness of the cylinder material and the maximum stress of the crack part of the cylinder in the thermal starting transient working condition of the nuclear turbine.
In one embodiment of the present disclosure, the second obtaining module 120 is further configured to: if the phased array detection crack depth is smaller than the stress corrosion crack growth size threshold value, determining the crack growth type as a first crack growth type; or if the phased array detection crack depth is greater than the stress corrosion crack growth size threshold, determining that the crack growth category is a second crack growth category.
In one embodiment of the disclosure, if the crack propagation category is a first crack propagation category, and the first crack propagation category includes two stages, wherein a crack size of the cylinder propagates from the phased array detection crack depth to the stress corrosion crack propagation size threshold in the first stage, and a crack size of the cylinder propagates from the stress corrosion crack propagation size threshold to the low cycle fatigue critical crack size in the second stage.
In one embodiment of the disclosure, if the crack propagation category is a second crack propagation category, and the second crack propagation category includes a stage, wherein a crack size of the cylinder propagates from the phased array inspection crack depth to the low cycle fatigue critical crack size at a first stage.
In one embodiment of the present disclosure, the first obtaining module 110 is further configured to:
obtaining a first stress corrosion crack growth life under the first crack growth category based on the stress corrosion crack growth size threshold value, a cylinder material annual average stress corrosion crack growth rate test value and a low cycle fatigue critical crack size of the cylinder under the cold starting transient working condition of the nuclear turbine;
obtaining a second stress corrosion crack growth life under the first crack growth category based on the stress corrosion crack growth size threshold value, a cylinder material annual average stress corrosion crack growth rate test value and a low cycle fatigue critical crack size of the cylinder under the nuclear turbine temperature starting transient working condition;
obtaining a third stress corrosion crack growth life under the first crack growth category based on the stress corrosion crack growth size threshold value, a cylinder material annual average stress corrosion crack growth rate test value and a low cycle fatigue critical crack size of the cylinder under the hot start transient condition of the nuclear turbine;
And determining the stress corrosion crack growth life under the first crack growth category based on a first stress corrosion crack growth life under the first crack growth category, a second stress corrosion crack growth life under the first crack growth category, and a third stress corrosion crack growth life under the first crack growth category.
In one embodiment of the present disclosure, the first obtaining module 110 is further configured to:
and determining the minimum value of the first stress corrosion crack extension life under the first crack extension category, the second stress corrosion crack extension life under the first crack extension category and the third stress corrosion crack extension life under the first crack extension category as the stress corrosion crack extension life under the first crack extension category.
In one embodiment of the present disclosure, the first obtaining module 110 is further configured to:
obtaining a first stress corrosion crack growth life under the second crack growth category based on the phased array detection crack depth, a cylinder material annual average stress corrosion crack growth rate test value and a low cycle fatigue critical crack size of the cylinder under the cold starting transient working condition of the nuclear turbine;
Obtaining a second stress corrosion crack growth life under the second crack growth category based on the phased array detection crack depth, a cylinder material annual average stress corrosion crack growth rate test value and a low cycle fatigue critical crack size of the cylinder under the nuclear turbine temperature starting transient working condition;
obtaining a third stress corrosion crack growth life under the second crack growth category based on the phased array detection crack depth, a cylinder material annual average stress corrosion crack growth rate test value and a low cycle fatigue critical crack size of the cylinder under the hot start transient state working condition of the nuclear turbine;
and determining the stress corrosion crack growth life under the second crack growth category based on the first stress corrosion crack growth life under the second crack growth category, the second stress corrosion crack growth life under the second crack growth category, and the third stress corrosion crack growth life under the second crack growth category.
In one embodiment of the present disclosure, the first obtaining module 110 is further configured to: and determining the minimum value of the first stress corrosion crack extension life under the second crack extension category, the second stress corrosion crack extension life under the second crack extension category and the third stress corrosion crack extension life under the second crack extension category as the stress corrosion crack extension life under the second crack extension category.
In one embodiment of the present disclosure, the first obtaining module 110 is further configured to:
obtaining the low cycle fatigue crack growth life of the first stage of the first crack growth class of the cold starting transient operating condition of the nuclear turbine based on the phased array detection crack depth, the stress corrosion crack growth size threshold value, the crack shape parameter of the cylinder, the low cycle fatigue crack growth test constant of cylinder materials and the maximum stress of the crack part of the cylinder of the cold starting transient operating condition of the nuclear turbine;
and obtaining the low cycle fatigue crack extension life of the first crack extension class second stage of the cold starting transient operating condition of the nuclear turbine based on the stress corrosion crack extension size threshold value, the low cycle fatigue critical crack size of the cylinder of the cold starting transient operating condition of the nuclear turbine, the crack shape parameter of the cylinder, the low cycle fatigue crack extension test constant of cylinder materials and the maximum stress of the crack part of the cylinder of the cold starting transient operating condition of the nuclear turbine.
In one embodiment of the present disclosure, the first obtaining module 110 is further configured to:
and obtaining the low cycle fatigue crack extension life of the first stage of the second crack extension class of the cold starting transient operating condition of the nuclear turbine based on the phased array detection crack depth, the low cycle fatigue critical crack size of the cylinder of the cold starting transient operating condition of the nuclear turbine, the crack shape parameter of the cylinder, the low cycle fatigue crack extension test constant of a cylinder material and the maximum stress of the crack part of the cylinder of the cold starting transient operating condition of the nuclear turbine.
In one embodiment of the present disclosure, the first obtaining module 110 is further configured to:
obtaining the low cycle fatigue crack growth life of the first stage of the first crack growth class of the nuclear turbine temperature starting transient operating condition based on the phased array detection crack depth, the stress corrosion crack growth size threshold value, the crack shape parameter of the cylinder, the cylinder material low cycle fatigue crack growth test constant and the maximum stress of the cylinder crack part of the nuclear turbine temperature starting transient operating condition;
and obtaining the low cycle fatigue crack extension life of the first crack extension class second stage of the nuclear turbine temperature starting transient state working condition based on the stress corrosion crack extension size threshold value, the low cycle fatigue critical crack size of the cylinder of the nuclear turbine temperature starting transient state working condition, the crack shape parameter of the cylinder, the low cycle fatigue crack extension test constant of cylinder materials and the maximum stress of the crack part of the cylinder of the nuclear turbine temperature starting transient state working condition.
In one embodiment of the present disclosure, the first obtaining module 110 is further configured to:
and obtaining the low cycle fatigue crack extension life of the first stage of the second crack extension class of the nuclear turbine temperature starting transient operating condition based on the phased array detection crack depth, the low cycle fatigue critical crack size of the cylinder of the nuclear turbine temperature starting transient operating condition, the crack shape parameter of the cylinder, the cylinder material low cycle fatigue crack extension test constant and the maximum stress of the cylinder crack part of the nuclear turbine temperature starting transient operating condition.
In one embodiment of the present disclosure, the first obtaining module 110 is further configured to:
obtaining the low cycle fatigue crack growth life of the first stage of the first crack growth class of the thermal starting transient operating condition of the nuclear turbine based on the phased array detection crack depth, the stress corrosion crack growth size threshold value, the crack shape parameter of the cylinder, the low cycle fatigue crack growth test constant of cylinder materials and the maximum stress of the crack part of the cylinder of the thermal starting transient operating condition of the nuclear turbine;
and obtaining the low cycle fatigue crack extension life of the first crack extension class second stage of the nuclear turbine thermal starting transient state working condition based on the stress corrosion crack extension size threshold value, the low cycle fatigue critical crack size of the cylinder of the nuclear turbine thermal starting transient state working condition, the crack shape parameter of the cylinder, the low cycle fatigue crack extension test constant of cylinder materials and the maximum stress of the crack part of the cylinder of the nuclear turbine thermal starting transient state working condition.
In one embodiment of the present disclosure, the first obtaining module 110 is further configured to:
and obtaining the low cycle fatigue crack extension life of the first stage of the second crack extension class of the thermal starting transient operating condition of the nuclear turbine based on the phased array detection crack depth, the low cycle fatigue critical crack size of the cylinder of the thermal starting transient operating condition of the nuclear turbine, the crack shape parameter of the cylinder, the low cycle fatigue crack extension test constant of cylinder materials and the maximum stress of the crack part of the cylinder of the thermal starting transient operating condition of the nuclear turbine.
In one embodiment of the present disclosure, the second obtaining module 120 is further configured to: and obtaining the crack propagation calendar life based on the stress corrosion crack propagation life and the multi-stage low cycle fatigue crack propagation life of the cylinder under the crack propagation category.
In one embodiment of the present disclosure, if the crack propagation category of the cylinder is the first crack propagation category, the second obtaining module 120 is further configured to:
obtaining a calendar life of the first crack growth type first stage based on a low cycle fatigue crack growth life of the first crack growth type first stage of the nuclear turbine cold start transient state operating condition, a low cycle fatigue crack growth life of the first crack growth type first stage of the nuclear turbine warm start transient state operating condition, an annual average cold start number, an annual average warm start number, and an annual average hot start number of the nuclear turbine;
obtaining a calendar life of the first crack growth type second stage based on a stress corrosion crack growth life under the first crack growth type, a low cycle fatigue crack growth life of the first crack growth type second stage of the cold start transient condition of the nuclear turbine, a low cycle fatigue crack growth life of the first crack growth type second stage of the warm start transient condition of the nuclear turbine, an annual average cold start number, an annual average warm start number, and an annual average hot start number of the nuclear turbine;
And obtaining the crack propagation calendar life based on the calendar life of the first stage of the first crack propagation class and the calendar life of the second stage of the first crack propagation class.
In one embodiment of the present disclosure, if the crack propagation category of the cylinder is the second crack propagation category, the second obtaining module 120 is further configured to:
obtaining a calendar life of the first stage of the second crack growth class based on a stress corrosion crack growth life under the second crack growth class, a low cycle fatigue crack growth life of the first stage of the second crack growth class of the cold start transient condition of the nuclear turbine, a low cycle fatigue crack growth life of the first stage of the second crack growth class of the warm start transient condition of the nuclear turbine, an annual average cold start number, an annual average warm start number, and an annual average hot start number of the nuclear turbine;
and obtaining the crack propagation calendar life based on the calendar life of the first stage of the second crack propagation class.
In one embodiment of the present disclosure, the monitoring module 130 is further configured to: if the nuclear turbine is in a manufacturing stage, a safety coefficient is obtained based on the crack propagation calendar life and the crack propagation life safety monitoring criterion value of the cylinder; judging whether the safety coefficient meets a first monitoring qualification condition or not so as to monitor the safety of the crack propagation life of the cylinder.
In one embodiment of the present disclosure, the monitoring module 130 is further configured to: if the safety coefficient does not meet the first monitoring qualification condition, acquiring abnormal data of the cylinder in the manufacturing stage; and optimizing and improving the abnormal data of the cylinder in the manufacturing stage, and returning to execute the process of acquiring the safety coefficient until the acquired safety coefficient meets the first monitoring qualification condition.
In one embodiment of the present disclosure, the monitoring module 130 is further configured to: if the nuclear turbine is in a use stage, obtaining a safety multiplying power based on the crack propagation calendar life and the planned overhaul interval of the nuclear turbine; and judging whether the safety multiplying power meets a second monitoring qualification condition or not so as to monitor the safety of the crack propagation life of the cylinder.
In one embodiment of the present disclosure, the monitoring module 130 is further configured to: if the safety multiplying power does not meet the second monitoring qualification condition, acquiring abnormal data of the cylinder in the using stage; and optimizing and improving the abnormal data of the cylinder in the using stage, and returning to execute the process of acquiring the safety multiplying power until the acquired safety multiplying power meets the second monitoring qualification condition.
It should be noted that, details not disclosed in the cylinder stress corrosion and low cycle fatigue safety monitoring device of the nuclear turbine according to the embodiments of the present disclosure are referred to details disclosed in the cylinder stress corrosion and low cycle fatigue safety monitoring method of the nuclear turbine according to the embodiments of the present disclosure, and are not described herein.
In summary, the device for monitoring cylinder stress corrosion and low cycle fatigue safety of a nuclear turbine according to the embodiments of the present disclosure acquires phased array detection crack depth of a cylinder of the nuclear turbine, acquires stress corrosion crack growth life and low cycle fatigue crack growth life of the cylinder under different crack growth categories, acquires crack growth category of the cylinder based on the phased array detection crack depth, acquires stress corrosion crack growth life and low cycle fatigue crack growth life of the cylinder based on the crack growth category of the cylinder, acquires crack growth calendar life of the cylinder, and performs crack growth life safety monitoring on the cylinder based on the crack growth calendar life. Therefore, the influences of stress corrosion and low cycle fatigue on the service life of the cylinder can be comprehensively considered, so that the safety monitoring of crack propagation service life of the cylinder is carried out, and the long-life safe operation of the cylinder of the nuclear turbine is ensured.
In order to implement the above embodiments, as shown in fig. 10, an embodiment of the present disclosure proposes an electronic device 200, including: the system comprises a memory 210, a processor 220 and a computer program stored in the memory 210 and capable of running on the processor 220, wherein the processor 220 realizes the cylinder stress corrosion and low cycle fatigue safety monitoring method of the nuclear turbine when executing the program.
In one embodiment of the present disclosure, the electronic device 200 further comprises: the wireless communication assembly is connected with the nuclear turbine, and data transmission is performed between the electronic equipment 200 and the nuclear turbine through the wireless communication assembly.
In one embodiment of the present disclosure, the memory 210 is configured to store a crack propagation calendar life of a cylinder of the nuclear turbine;
the processor 220 is configured to obtain a crack growth life safety monitoring instruction, obtain a crack growth calendar life of a target cylinder of the nuclear turbine to be monitored from the memory 210 based on the crack growth life safety monitoring instruction, and perform crack growth life safety monitoring on the target cylinder based on the crack growth calendar life of the target cylinder.
In one embodiment of the present disclosure, the electronic device 200 further comprises: a remote client, the remote client being coupled to the processor 220; the remote client is configured to send the crack growth life safety monitoring instruction to the processor 220, and receive a monitoring result fed back by the processor 220.
In one embodiment of the disclosure, the remote client is further configured to obtain control information of a user who controls the remote client, and generate the crack growth life safety monitoring instruction based on the control information.
In one embodiment of the present disclosure, the processor 220 is further configured to determine a cylinder of the remote client associated nuclear turbine as the target cylinder.
According to the electronic equipment disclosed by the embodiment of the disclosure, a computer program stored on a memory is executed through a processor, the phased array detection crack depth of the cylinder of the nuclear turbine is obtained, the stress corrosion crack extension life and the low cycle fatigue crack extension life of the cylinder under different crack extension categories are obtained, the crack extension category of the cylinder is obtained based on the phased array detection crack depth, the stress corrosion crack extension life and the low cycle fatigue crack extension life of the cylinder are obtained based on the crack extension category of the cylinder, the crack extension calendar life of the cylinder is obtained, and the crack extension life safety monitoring is performed on the cylinder based on the crack extension calendar life. Therefore, the influences of stress corrosion and low cycle fatigue on the service life of the cylinder can be comprehensively considered, so that the safety monitoring of crack propagation service life of the cylinder is carried out, and the long-life safe operation of the cylinder of the nuclear turbine is ensured.
In order to achieve the above embodiments, the embodiments of the present disclosure provide a computer readable storage medium having a computer program stored thereon, which when executed by a processor, implements the above method for monitoring cylinder stress corrosion and low cycle fatigue safety of a nuclear turbine.
The computer readable storage medium of the embodiment of the disclosure obtains a phased array detection crack depth of a cylinder of a nuclear turbine through storing a computer program and executing the phased array detection crack depth by a processor, obtains stress corrosion crack extension life and low cycle fatigue crack extension life of the cylinder under different crack extension categories, obtains the crack extension category of the cylinder based on the phased array detection crack depth, obtains the crack extension calendar life of the cylinder based on the stress corrosion crack extension life and the low cycle fatigue crack extension life of the cylinder, and monitors the crack extension life safety of the cylinder based on the crack extension calendar life. Therefore, the influences of stress corrosion and low cycle fatigue on the service life of the cylinder can be comprehensively considered, so that the safety monitoring of crack propagation service life of the cylinder is carried out, and the long-life safe operation of the cylinder of the nuclear turbine is ensured.
In order to achieve the above embodiments, an embodiment of the present disclosure provides a monitoring platform suitable for a nuclear turbine, including the cylinder stress corrosion and low cycle fatigue safety monitoring device of the nuclear turbine shown in fig. 9; or the electronic device described above; or a computer readable storage medium as described above.
According to the monitoring platform suitable for the nuclear turbine, the phased array detection crack depth of the cylinder of the nuclear turbine is obtained, the stress corrosion crack extension life and the low cycle fatigue crack extension life of the cylinder under different crack extension categories are obtained, the crack extension category of the cylinder is obtained based on the phased array detection crack depth, the crack extension calendar life of the cylinder is obtained based on the stress corrosion crack extension life and the low cycle fatigue crack extension life of the cylinder, and the crack extension life safety monitoring is carried out on the cylinder based on the crack extension calendar life. Therefore, the influences of stress corrosion and low cycle fatigue on the service life of the cylinder can be comprehensively considered, so that the safety monitoring of crack propagation service life of the cylinder is carried out, and the long-life safe operation of the cylinder of the nuclear turbine is ensured.
In the description of the present disclosure, it should be understood that the terms "center", "longitudinal", "lateral", "length", "width", "thickness", "upper", "lower", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", "clockwise", "counterclockwise", "axial", "radial", "circumferential", etc. indicate orientations or positional relationships based on the orientations or positional relationships shown in the drawings are merely for convenience in describing the present disclosure and simplifying the description, and do not indicate or imply that the device or element being referred to must have a specific orientation, be configured and operated in a specific orientation, and therefore should not be construed as limiting the present disclosure.
Furthermore, the terms "first," "second," and the like, are used for descriptive purposes only and are not to be construed as indicating or implying a relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defining "a first" or "a second" may explicitly or implicitly include one or more such feature. In the description of the present disclosure, the meaning of "a plurality" is two or more, unless explicitly defined otherwise.
In the present disclosure, unless explicitly specified and limited otherwise, the terms "mounted," "connected," "secured," and the like are to be construed broadly, and may be, for example, fixedly connected, detachably connected, or integrally formed; can be mechanically or electrically connected; can be directly connected or indirectly connected through an intermediate medium, and can be communicated with the inside of two elements or the interaction relationship of the two elements. The specific meaning of the terms in this disclosure will be understood by those of ordinary skill in the art as the case may be.
In this disclosure, unless expressly stated or limited otherwise, a first feature "up" or "down" a second feature may be the first and second features in direct contact, or the first and second features in indirect contact through an intervening medium. Moreover, a first feature being "above," "over" and "on" a second feature may be a first feature being directly above or obliquely above the second feature, or simply indicating that the first feature is level higher than the second feature. The first feature being "under", "below" and "beneath" the second feature may be the first feature being directly under or obliquely below the second feature, or simply indicating that the first feature is less level than the second feature.
In the description of the present specification, a description referring to terms "one embodiment," "some embodiments," "examples," "specific examples," or "some examples," etc., means that a particular feature, structure, material, or characteristic described in connection with the embodiment or example is included in at least one embodiment or example of the present disclosure. In this specification, schematic representations of the above terms are not necessarily directed to the same embodiment or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments or examples. Furthermore, the different embodiments or examples described in this specification and the features of the different embodiments or examples may be combined and combined by those skilled in the art without contradiction.
Although embodiments of the present disclosure have been shown and described above, it will be understood that the above embodiments are illustrative and not to be construed as limiting the present disclosure, and that variations, modifications, alternatives, and variations may be made to the above embodiments by one of ordinary skill in the art within the scope of the present disclosure.
Claims (29)
1. A cylinder stress corrosion and low cycle fatigue safety monitoring method of a nuclear turbine is characterized by comprising the following steps:
Acquiring phased array detection crack depth of a cylinder of a nuclear turbine, and acquiring stress corrosion crack extension life and low cycle fatigue crack extension life of the cylinder under different crack extension categories;
detecting crack depth based on the phased array, obtaining a crack growth class of the cylinder, and obtaining a crack growth calendar life of the cylinder based on stress corrosion crack growth life and low cycle fatigue crack growth life of the cylinder under the crack growth class;
and based on the crack propagation calendar life, performing crack propagation life safety monitoring on the cylinder.
2. The method of claim 1, wherein the obtaining a phased array of cylinders of a nuclear turbine detects crack depths, comprising:
the phased array ultrasonic flaw detector and the phased array probe are used for carrying out phased array detection on the cylinder to obtain the phased array detection crack depth;
and if no crack is found in the phased array detection of the cylinder, setting the depth of the phased array detection crack as a set value.
3. The method of claim 1, wherein the obtaining a crack propagation category for the cylinder based on the phased array detection crack depth comprises:
Acquiring a crack extension size set of the cylinder;
and acquiring the crack propagation category of the cylinder based on the phased array detection crack depth and the crack propagation size set.
4. The method of claim 3, wherein the obtaining a set of crack propagation sizes for the cylinder comprises:
acquiring stress calculation basic data of the cylinder;
acquiring material test basic data of the cylinder;
the set of crack growth dimensions is determined based on the stress calculation basis data and the material experiment basis data.
5. The method of claim 4, wherein the determining the set of crack growth dimensions based on the stress calculation basis data and the material experiment basis data comprises:
determining a stress corrosion crack propagation size threshold value of the cylinder based on the crack shape parameter of the cylinder, the stress corrosion fracture toughness of a cylinder material and the maximum stress of a crack part of the cylinder under load running steady-state working condition of the nuclear turbine;
determining the low cycle fatigue critical crack size of the cylinder in the cold starting transient working condition of the nuclear turbine based on the crack shape parameter of the cylinder, the fracture toughness of the cylinder material and the maximum stress of the crack part of the cylinder in the cold starting transient working condition of the nuclear turbine;
Determining the low cycle fatigue critical crack size of the cylinder of the nuclear turbine temperature starting transient working condition based on the crack shape parameter of the cylinder, the fracture toughness of the cylinder material and the maximum stress of the crack part of the cylinder of the nuclear turbine temperature starting transient working condition;
and determining the low cycle fatigue critical crack size of the cylinder in the thermal starting transient working condition of the nuclear turbine based on the crack shape parameter of the cylinder, the fracture toughness of the cylinder material and the maximum stress of the crack part of the cylinder in the thermal starting transient working condition of the nuclear turbine.
6. The method of claim 5, wherein the obtaining a crack propagation category for the cylinder based on the phased array detection crack depth and the set of crack propagation dimensions comprises:
if the phased array detection crack depth is smaller than the stress corrosion crack growth size threshold value, determining the crack growth type as a first crack growth type; or alternatively, the process may be performed,
and if the phased array detection crack depth is larger than the stress corrosion crack growth size threshold value, determining that the crack growth type is a second crack growth type.
7. The method of claim 6, wherein obtaining stress corrosion crack growth life under different crack growth categories comprises:
Obtaining a first stress corrosion crack growth life under the first crack growth category based on the stress corrosion crack growth size threshold value, a cylinder material annual average stress corrosion crack growth rate test value and a low cycle fatigue critical crack size of the cylinder under the cold starting transient working condition of the nuclear turbine;
obtaining a second stress corrosion crack growth life under the first crack growth category based on the stress corrosion crack growth size threshold value, a cylinder material annual average stress corrosion crack growth rate test value and a low cycle fatigue critical crack size of the cylinder under the nuclear turbine temperature starting transient working condition;
obtaining a third stress corrosion crack growth life under the first crack growth category based on the stress corrosion crack growth size threshold value, a cylinder material annual average stress corrosion crack growth rate test value and a low cycle fatigue critical crack size of the cylinder under the hot start transient condition of the nuclear turbine;
and determining the stress corrosion crack growth life under the first crack growth category based on a first stress corrosion crack growth life under the first crack growth category, a second stress corrosion crack growth life under the first crack growth category, and a third stress corrosion crack growth life under the first crack growth category.
8. The method of claim 6, wherein obtaining stress corrosion crack growth life under different crack growth categories comprises:
obtaining a first stress corrosion crack growth life under the second crack growth category based on the phased array detection crack depth, a cylinder material annual average stress corrosion crack growth rate test value and a low cycle fatigue critical crack size of the cylinder under the cold starting transient working condition of the nuclear turbine;
obtaining a second stress corrosion crack growth life under the second crack growth category based on the phased array detection crack depth, a cylinder material annual average stress corrosion crack growth rate test value and a low cycle fatigue critical crack size of the cylinder under the nuclear turbine temperature starting transient working condition;
obtaining a third stress corrosion crack growth life under the second crack growth category based on the phased array detection crack depth, a cylinder material annual average stress corrosion crack growth rate test value and a low cycle fatigue critical crack size of the cylinder under the hot start transient state working condition of the nuclear turbine;
and determining the stress corrosion crack growth life under the second crack growth category based on the first stress corrosion crack growth life under the second crack growth category, the second stress corrosion crack growth life under the second crack growth category, and the third stress corrosion crack growth life under the second crack growth category.
9. The method of claim 6, wherein obtaining low cycle fatigue crack growth life under different crack growth categories comprises:
obtaining the low cycle fatigue crack growth life of the first stage of the first crack growth class of the cold starting transient operating condition of the nuclear turbine based on the phased array detection crack depth, the stress corrosion crack growth size threshold value, the crack shape parameter of the cylinder, the low cycle fatigue crack growth test constant of cylinder materials and the maximum stress of the crack part of the cylinder of the cold starting transient operating condition of the nuclear turbine;
and obtaining the low cycle fatigue crack extension life of the first crack extension class second stage of the cold starting transient operating condition of the nuclear turbine based on the stress corrosion crack extension size threshold value, the low cycle fatigue critical crack size of the cylinder of the cold starting transient operating condition of the nuclear turbine, the crack shape parameter of the cylinder, the low cycle fatigue crack extension test constant of cylinder materials and the maximum stress of the crack part of the cylinder of the cold starting transient operating condition of the nuclear turbine.
10. The method of claim 6, wherein obtaining low cycle fatigue crack growth life under different crack growth categories comprises:
And obtaining the low cycle fatigue crack extension life of the first stage of the second crack extension class of the cold starting transient operating condition of the nuclear turbine based on the phased array detection crack depth, the low cycle fatigue critical crack size of the cylinder of the cold starting transient operating condition of the nuclear turbine, the crack shape parameter of the cylinder, the low cycle fatigue crack extension test constant of a cylinder material and the maximum stress of the crack part of the cylinder of the cold starting transient operating condition of the nuclear turbine.
11. The method of claim 6, wherein the deriving the crack growth calendar life of the cylinder based on stress corrosion crack growth life and low cycle fatigue crack growth life under the crack growth category of the cylinder comprises:
and obtaining the crack propagation calendar life based on the stress corrosion crack propagation life and the multi-stage low cycle fatigue crack propagation life of the cylinder under the crack propagation category.
12. The method of claim 11, wherein if the crack growth category of the cylinder is the first crack growth category, the deriving the crack growth calendar life based on stress corrosion crack growth life and multi-stage low cycle fatigue crack growth life under the crack growth category of the cylinder comprises:
Obtaining a calendar life of the first crack growth type first stage based on a low cycle fatigue crack growth life of the first crack growth type first stage of the nuclear turbine cold start transient state operating condition, a low cycle fatigue crack growth life of the first crack growth type first stage of the nuclear turbine warm start transient state operating condition, an annual average cold start number, an annual average warm start number, and an annual average hot start number of the nuclear turbine;
obtaining a calendar life of the first crack growth type second stage based on a stress corrosion crack growth life under the first crack growth type, a low cycle fatigue crack growth life of the first crack growth type second stage of the cold start transient condition of the nuclear turbine, a low cycle fatigue crack growth life of the first crack growth type second stage of the warm start transient condition of the nuclear turbine, an annual average cold start number, an annual average warm start number, and an annual average hot start number of the nuclear turbine;
And obtaining the crack propagation calendar life based on the calendar life of the first stage of the first crack propagation class and the calendar life of the second stage of the first crack propagation class.
13. The method of claim 11, wherein if the crack growth category of the cylinder is the second crack growth category, the deriving the crack growth calendar life based on stress corrosion crack growth life and multi-stage low cycle fatigue crack growth life under the crack growth category of the cylinder comprises:
obtaining a calendar life of the first stage of the second crack growth class based on a stress corrosion crack growth life under the second crack growth class, a low cycle fatigue crack growth life of the first stage of the second crack growth class of the cold start transient condition of the nuclear turbine, a low cycle fatigue crack growth life of the first stage of the second crack growth class of the warm start transient condition of the nuclear turbine, an annual average cold start number, an annual average warm start number, and an annual average hot start number of the nuclear turbine;
And obtaining the crack propagation calendar life based on the calendar life of the first stage of the second crack propagation class.
14. The method of any of claims 1-13, wherein the crack propagation life safety monitoring of the cylinder based on the crack propagation calendar life comprises:
if the nuclear turbine is in a manufacturing stage, a safety coefficient is obtained based on the crack propagation calendar life and the crack propagation life safety monitoring criterion value of the cylinder;
judging whether the safety coefficient meets a first monitoring qualification condition or not so as to monitor the safety of the crack propagation life of the cylinder.
15. The method of claim 14, wherein the method further comprises:
if the safety coefficient does not meet the first monitoring qualification condition, acquiring abnormal data of the cylinder in the manufacturing stage;
and optimizing and improving the abnormal data of the cylinder in the manufacturing stage, and returning to execute the process of acquiring the safety coefficient until the acquired safety coefficient meets the first monitoring qualification condition.
16. The method of any of claims 1-13, wherein the crack propagation life safety monitoring of the cylinder based on the crack propagation calendar life comprises:
If the nuclear turbine is in a use stage, obtaining a safety multiplying power based on the crack propagation calendar life and the planned overhaul interval of the nuclear turbine;
and judging whether the safety multiplying power meets a second monitoring qualification condition or not so as to monitor the safety of the crack propagation life of the cylinder.
17. The method of claim 16, wherein the method further comprises:
if the safety multiplying power does not meet the second monitoring qualification condition, acquiring abnormal data of the cylinder in the using stage;
and optimizing and improving the abnormal data of the cylinder in the using stage, and returning to execute the process of acquiring the safety multiplying power until the acquired safety multiplying power meets the second monitoring qualification condition.
18. The utility model provides a cylinder stress corrosion and low cycle fatigue safety monitoring device of nuclear turbine which characterized in that includes:
the first acquisition module is used for acquiring phased array detection crack depth of a cylinder of the nuclear turbine and acquiring stress corrosion crack extension life and low cycle fatigue crack extension life of the cylinder under different crack extension categories;
the second acquisition module is used for detecting crack depth based on the phased array, acquiring crack extension types of the cylinder, and acquiring crack extension calendar life of the cylinder based on stress corrosion crack extension life and low cycle fatigue crack extension life of the cylinder under the crack extension types;
And the monitoring module is used for carrying out crack extension service life safety monitoring on the cylinder based on the crack extension calendar service life.
19. The apparatus of claim 18, wherein the first acquisition module is further configured to:
the phased array ultrasonic flaw detector and the phased array probe are used for carrying out phased array detection on the cylinder to obtain the phased array detection crack depth;
and if no crack is found in the phased array detection of the cylinder, setting the depth of the phased array detection crack as a set value.
20. The apparatus of claim 18, wherein the second acquisition module is further configured to:
acquiring a crack extension size set of the cylinder;
and acquiring the crack propagation category of the cylinder based on the phased array detection crack depth and the crack propagation size set.
21. The apparatus of claim 20, wherein the second acquisition module is further configured to:
acquiring stress calculation basic data of the cylinder;
acquiring material test basic data of the cylinder;
the set of crack growth dimensions is determined based on the stress calculation basis data and the material experiment basis data.
22. The apparatus of any one of claims 18-21, wherein the monitoring module is further configured to:
if the nuclear turbine is in a use stage, obtaining a safety multiplying power based on the crack propagation calendar life and the planned overhaul interval of the nuclear turbine;
and judging whether the safety multiplying power meets a second monitoring qualification condition or not so as to monitor the safety of the crack propagation life of the cylinder.
23. The apparatus of claim 22, wherein the monitoring module is further configured to:
if the safety multiplying power does not meet the second monitoring qualification condition, acquiring abnormal data of the cylinder in the using stage;
and optimizing and improving the abnormal data of the cylinder in the using stage, and returning to execute the process of acquiring the safety multiplying power until the acquired safety multiplying power meets the second monitoring qualification condition.
24. An electronic device, comprising: a memory, a processor and a computer program stored on the memory and executable on the processor, the processor implementing the method for cylinder stress corrosion and low cycle fatigue safety monitoring of a nuclear turbine according to any of claims 1-17 when the program is executed.
25. The electronic device of claim 24, further comprising: the wireless communication assembly is connected with the nuclear turbine, and data transmission is performed between the electronic equipment and the nuclear turbine through the wireless communication assembly.
26. The electronic device of claim 24, wherein the memory is configured to store a crack propagation calendar life of a cylinder of the nuclear turbine;
the processor is used for acquiring a crack extension life safety monitoring instruction, acquiring the crack extension calendar life of a target cylinder of the nuclear turbine to be monitored from the memory based on the crack extension life safety monitoring instruction, and performing crack extension life safety monitoring on the target cylinder based on the crack extension calendar life of the target cylinder.
27. The electronic device of claim 26, further comprising: the remote client is connected with the processor;
the remote client is used for sending the crack growth life safety monitoring instruction to the processor and receiving the monitoring result fed back by the processor.
28. A computer readable storage medium having stored thereon a computer program, which when executed by a processor implements the cylinder stress corrosion and low cycle fatigue safety monitoring method of a nuclear turbine according to any of claims 1-17.
29. A monitoring platform for a nuclear turbine, comprising: a cylinder stress corrosion and low cycle fatigue safety monitoring device for a nuclear turbine according to any one of claims 18 to 23; or an electronic device as claimed in any one of claims 24-27; or a computer readable storage medium as claimed in claim 28.
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