Nuclear power plant valve sealing life prediction method and device

Abstract

The invention particularly relates to a nuclear power plant valve sealing life prediction method. The method comprises the steps of obtaining one-step state transition data of same-type valves of a nuclear power plant; constructing a one-step state transition frequency matrix of the same type of valves; calculating a state transition probability matrix of the same type of valves; calculating a state transition probability matrix of the same type of valves in x refueling cycles; obtaining a service life prediction table of the same type of valves with the initial sealing grade of j grade in x refueling cycles; predicting the service life of the valves of the same type in x times of refueling circulation with the initial sealing grade of j grade; j is one of 1, 2, 3, 4, 5 and 6. The invention further relates to a nuclear power plant valve sealing life prediction device, computer equipment and a storage medium. According to the method, the sealing life of the nuclear power plant valves with different initial sealing grades is predicted, and basic data support is provided for subsequent preventative maintenance optimization, predictive maintenance and other work.

Description

Technical Field

[0001] The invention relates to the technical field of nuclear power plant valve maintenance, and in particular to a method and device for predicting the sealing life of nuclear power plant valves. Background Art

[0002] There are many valves in nuclear power plants, and their function is to perform high-reliability switching. When the valves in nuclear power plants cannot be closed reliably and internal leakage occurs, it means that their sealing life has ended. In terms of reliability management, the prediction of the sealing life of nuclear power plant valves is the basis for preventive maintenance and predictive maintenance of nuclear power plant valves. However, there is currently no method to predict the sealing life of nuclear power plant valves, which makes it difficult to carry out preventive maintenance and predictive maintenance of nuclear power plant valves.

[0003] The sealing failure of nuclear power plant valves is generally a gradual process. Nuclear power plant valves will not suddenly change from a good sealing state to a failed sealing state. During the entire maintenance interval, the nuclear power plant valves experience a process of gradual accumulation of damage and a qualitative change from quantitative change. However, the sealing failure of nuclear power plant valves is also random. Its failure factors are at the microscopic micron level, and it also involves the elastic-plastic deformation and friction factors of the material, and there are a large number of random factors. These factors affect each other, and these influencing factors themselves show a certain degree of randomness, and in their relationship with the sealing of nuclear power plant valves, they show a certain ambiguity; moreover, much of the information characterizing the sealing failure of nuclear power plants is unclear, and some of the information is not fully collected. Therefore, it is difficult to find a one-to-one corresponding functional relationship between the sealing failure of nuclear power plants and various influencing factors, and it is difficult to describe all or most of them using precise mathematical and mechanical methods. Summary of the invention

[0004] The purpose of the present invention is to provide a method and device for predicting the sealing life of nuclear power plant valves. For the random process of nuclear power plant valve sealing failure, according to the maintenance and detection rules of nuclear power plants, the refueling cycle is used as the degradation node, and the historical sealing test data of nuclear power plant valves are processed in combination with the nuclear power plant valve multi-state sealing grading method, so as to realize the sealing life prediction of nuclear power plant valves with different initial sealing levels, and provide basic data support for subsequent preventive maintenance optimization, predictive maintenance and other work.

[0005] In order to achieve the above object, the present invention provides the following technical solutions:

[0006] A method for predicting the sealing life of valves in a nuclear power plant comprises the following steps:

[0007] S101, obtaining one-step state transfer data of valves of the same type in a nuclear power plant;

[0008] S102, constructing a one-step state transition frequency matrix F of valves of the same type according to the one-step state transition data of valves of the same type;

[0009] S103, calculating a state transition probability matrix P of valves of the same type according to a one-step state transition frequency matrix F of valves of the same type;

[0010] S104, based on the state transition probability matrix P of the same type of valve, calculate the state transition probability matrix P of the same type of valve within x material replacement cycles x ;

[0011] S105, based on the state transition probability matrix P of the same type of valve in x times of material replacement cycle x , get the life prediction table of the same type of valve with initial sealing level j and x refueling cycles;

[0012] S106, predicting the life of the same type of valve with initial sealing level j within x refueling cycles according to the life prediction table of the same type of valve with initial sealing level j within x refueling cycles;

[0013] j is one of 1, 2, 3, 4, 5, and 6.

[0014] Furthermore, in S101, the state transition data of various types of valves in the nuclear power plant is obtained, including the following steps:

[0015] S1011. Collect historical sealing test data of valves in nuclear power plants to obtain a first data sequence;

[0016] S1012, adding sealing level field information to the data in the first data sequence to obtain a second data sequence;

[0017] S1013, performing data processing on the data in the second data sequence to obtain a data sequence {X(n)} of valves of the same type;

[0018] S1014. Add one-step state transfer field information to the data in the data sequence ﹛X(n)﹜ of the same type of valves to obtain one-step state transfer data of the same type of valves.

[0019] Furthermore, in S1011, the historical sealing test data of the nuclear power plant valves are data obtained from sealing tests conducted on various valves of the nuclear power plant during each historical refueling cycle, and the historical sealing test data of the nuclear power plant valves are collected with one refueling cycle as one data collection interval; the data in the first data sequence includes the following field information: valve type, equipment code, leakage rate and the refueling cycle in which the test is conducted.

[0020] Furthermore, in S1012, the sealing level field information is added to the data in the first data sequence to obtain the second data sequence, including the following steps:

[0021] The equipment code is used as the unique identification of the valve. The sealing level of each valve in the nuclear power plant is evenly divided into 6 levels according to the leakage rate threshold of each valve in the nuclear power plant. Among them, the sealing performance of levels 1 to 5 decreases in sequence, with level 5 being the maximum allowable leakage rate and level 6 being unqualified.

[0022] For each piece of data in the first data sequence, the leakage rate thresholds of each level of the corresponding valve are obtained according to the device code field information, and then the sealing level to which the leakage rate field information of the piece of data belongs is determined according to the leakage rate thresholds of each level of the corresponding valve, and the sealing level field information is added to the piece of data to obtain the second data sequence;

[0023] The upper limit of the leakage rate threshold of each level of nuclear power plant valves = (the level / 5)*the maximum allowable leakage rate of nuclear power plant valves.

[0024] Furthermore, in S1013, data in the second data sequence is processed to obtain a data sequence {X(n)} of valves of the same type, including the following steps:

[0025] The data in the second data sequence whose sealing level difference between the same valve and the previous material replacement cycle is 2 or more are deleted as invalid data to obtain a third data sequence;

[0026] Then, the data in the third data sequence is divided according to the valve type field information, and the data with the same valve type field information constitutes a data sequence;

[0027] In the data sequence consisting of data with the same valve type field information, the data with the same device code field information are arranged in chronological order, and finally all the data are sorted to obtain the data sequence {X(n)} of the valve type.

[0028] Further, in S1014, one-step state transition field information is added to the data in the data sequence {X(n)} of the same type of valves to obtain one-step state transition data of the same type of valves, including the following steps:

[0029] Calculate the one-step state transition field information of the same valve data in the data sequence ﹛X(n)﹜ of the same type of valves, and exclude the one-step state transition field information caused by external human factors (maintenance activities), and obtain the one-step state transition data of the same type of valves;

[0030] The one-step state transfer field information of the same valve data is the change in the sealing level of the same valve after a material replacement cycle.

[0031] Further, in S102, based on the one-step state transition data of the same type of valves, a one-step state transition frequency matrix F of the same type of valves is constructed, including the following steps:

[0032] According to the one-step state transfer data of the same type of valve, the frequency of the same type of valve's sealing level changing from j to k after a material replacement cycle is counted respectively, and the one-step state transfer frequency data F of the same type of valve is obtained. jk ; j and k are both one of 1, 2, 3, 4, 5, 6;

[0033] According to the one-step state transfer frequency data F of the same type of valve jk , construct the one-step state transition frequency matrix F of the same type of valve:

[0034]

[0035] Further, in S103, the state transition probability matrix P of the same type of valves is calculated according to the one-step state transition frequency matrix F of the same type of valves:

[0036]

[0037] P jk is the state transition probability data of the same type of valve, which is calculated by the probability of the sealing level of the same type of valve transferring from j to k; j and k are both one of 1, 2, 3, 4, 5, and 6;

[0038]

[0039] Further, in S104, according to the state transition probability matrix P of the same type of valve, the state transition probability matrix P of the same type of valve within x material replacement cycles is calculated by matrix multiplication. x :

[0040] P x =P x-1 *P

[0041]

[0042] x is a natural number greater than or equal to 1.

[0043] Preferably, x takes the value 20.

[0044] Further, in S105, according to the state transition probability matrix P of the same type of valve in x times of material replacement cycle, x , we can get the life prediction table of the same type of valve with initial sealing level j and x refueling cycles:

[0045]

[0046]

[0047] Further, in S106, according to the life prediction table of the same type of valves with initial sealing level of j level within x refueling cycles, the life of the same type of valves with initial sealing level of j level within x refueling cycles is predicted, including the following steps:

[0048] For the same type of valve, the initial sealing level is level j. From the first to the xth refueling cycle, the number of refueling cycles when the probability of the sealing level state transitioning to level 6 is the largest is the predicted life of the valve of this type.

[0049] For the same type of valve with initial sealing level of level j, from the first to the xth refueling cycle, the number of refueling cycles when the sum of the probabilities of the sealing level state transitioning to level 1-5 is greater than or equal to 50% is the predicted median life of the valve of this type;

[0050] For the same type of valve with initial sealing level j from the 1st to the xth refueling cycle, the number of refueling cycles when the sum of the probabilities of the sealing level state transitioning to level 1-5 is greater than or equal to 36.8% is the predicted characteristic life of this type of valve.

[0051] The present invention also provides a device for predicting the life of valve seals in a nuclear power plant, comprising:

[0052] The first module 201 is used to obtain one-step state transfer data of valves of the same type in a nuclear power plant;

[0053] The second module 202 is used to construct a one-step state transition frequency matrix F of the same type of valves according to the one-step state transition data of the same type of valves;

[0054] The third module 203 is used to calculate the state transition probability matrix P of the same type of valves according to the one-step state transition frequency matrix F of the same type of valves;

[0055] The fourth module 204 is used to calculate the state transition probability matrix P of the same type of valve within x material replacement cycles according to the state transition probability matrix P of the same type of valve. x ;

[0056] The fifth module 205 is used to calculate the state transition probability matrix P of the same type of valve within x refueling cycles. x , get the life prediction table of the same type of valve with initial sealing level j and x refueling cycles;

[0057] The sixth module 206 is used to predict the life of the same type of valve with initial sealing level j within x refueling cycles according to the life prediction table of the same type of valve with initial sealing level j within x refueling cycles;

[0058] The first module 201 , the second module 202 , the third module 203 , the fourth module 204 , the fifth module 205 and the sixth module 206 are communicatively connected with each other.

[0059] The present invention also provides a computer device, including a memory and a processor, wherein the memory stores computer-readable instructions, and the processor implements the steps of the above-mentioned nuclear power plant valve seal life prediction method when executing the computer-readable instructions.

[0060] The present invention also provides a computer-readable storage medium, on which computer-readable instructions are stored, and when the computer-readable instructions are executed, the steps of the above-mentioned nuclear power plant valve seal life prediction method are implemented.

[0061] Beneficial technical effects of the present invention:

[0062] The method, device, computer equipment and storage medium for predicting the sealing life of nuclear power plant valves of the present invention process the random process of sealing failure of nuclear power plant valves according to the maintenance and detection rules of nuclear power plants, take the refueling cycle as the degradation node, and combine the multi-state sealing grading method of nuclear power plant valves to process the historical sealing test data of nuclear power plant valves, so as to realize the sealing life prediction of nuclear power plant valves with different initial sealing levels, and provide basic data support for subsequent preventive maintenance optimization, predictive maintenance and other work. BRIEF DESCRIPTION OF THE DRAWINGS

[0063] Figure 1 A flowchart of an embodiment of a method for predicting the sealing life of a valve in a nuclear power plant according to the present invention;

[0064] Figure 2 It is a structural schematic diagram of an embodiment of a device for predicting the sealing life of a valve in a nuclear power plant according to the present invention;

[0065] Figure 3 The figure is a schematic diagram of the structure of a computer device according to an embodiment of the present invention. DETAILED DESCRIPTION

[0066] Unless otherwise defined, all technical and scientific terms used herein have the same meaning as those commonly understood by technicians in the technical field of this application; the terms used in the specification of the application are only for the purpose of describing specific embodiments and are not intended to limit this application; the term "including" and any variation thereof in the specification and claims of this application and the above-mentioned drawings are intended to cover non-exclusive inclusions. The terms "first", "second", etc. in the specification and claims of this application or the above-mentioned drawings are used to distinguish different objects, not to describe a specific order.

[0067] Reference to "embodiments" herein means that a particular feature, structure, or characteristic described in conjunction with the embodiments may be included in at least one embodiment of the present application. The appearance of the phrase in various locations in the specification does not necessarily refer to the same embodiment, nor is it an independent or alternative embodiment that is mutually exclusive with other embodiments. It is explicitly and implicitly understood by those skilled in the art that the embodiments described herein may be combined with other embodiments.

[0068] The technical solution of the present invention is clearly and completely described below in conjunction with the accompanying drawings and specific embodiments.

[0069] refer to Figure 1 , shows a flow chart of an embodiment of a method for predicting the life of a valve seal in a nuclear power plant, the method for predicting the life of a valve seal in a nuclear power plant comprising the following steps:

[0070] S101, obtaining one-step state transfer data of valves of the same type in a nuclear power plant;

[0071] S102, constructing a one-step state transition frequency matrix F of valves of the same type according to the one-step state transition data of valves of the same type;

[0072] S103, calculating a state transition probability matrix P of valves of the same type according to a one-step state transition frequency matrix F of valves of the same type;

[0073] S104, based on the state transition probability matrix P of the same type of valve, calculate the state transition probability matrix P of the same type of valve within x material replacement cycles x ;

[0074] S105, based on the state transition probability matrix P of the same type of valve in x times of material replacement cycle x , get the life prediction table of the same type of valve with initial sealing level j and x refueling cycles;

[0075] S106, predicting the life of the same type of valve with initial sealing level j within x refueling cycles according to the life prediction table of the same type of valve with initial sealing level j within x refueling cycles;

[0076] j is one of 1, 2, 3, 4, 5, and 6.

[0077] In this embodiment, in S101, obtaining state transition data of various types of valves in a nuclear power plant includes the following steps:

[0078] S1011. Collect historical sealing test data of valves in nuclear power plants to obtain a first data sequence;

[0079] S1012, adding sealing level field information to the data in the first data sequence to obtain a second data sequence;

[0080] S1013, performing data processing on the data in the second data sequence to obtain a data sequence {X(n)} of valves of the same type;

[0081] S1014. Add one-step state transfer field information to the data in the data sequence ﹛X(n)﹜ of the same type of valves to obtain one-step state transfer data of the same type of valves.

[0082] In this embodiment, in S1011, the historical sealing test data of the nuclear power plant valves are data obtained from the sealing tests conducted on each valve of the nuclear power plant during each historical refueling cycle, and the historical sealing test data of the nuclear power plant valves are collected according to one refueling cycle as one data collection interval; the data in the first data sequence includes the following field information: valve type, equipment code, leakage rate and the refueling cycle in which the test is conducted.

[0083] As an example, the first data sequence is shown in Table 1.

[0084] Table 1 The first data sequence

[0085]

[0086]

[0087] In this embodiment, in S1012, adding sealing level field information to the data in the first data sequence to obtain the second data sequence includes the following steps:

[0088] The equipment code is used as the unique identification of the valve. The sealing level of each valve in the nuclear power plant is evenly divided into 6 levels according to the leakage rate threshold of each valve in the nuclear power plant. Among them, the sealing performance of levels 1 to 5 decreases in sequence, with level 5 being the maximum allowable leakage rate and level 6 being unqualified.

[0089] For each piece of data in the first data sequence, the leakage rate thresholds of each level of the corresponding valve are obtained according to the device code field information, and then the sealing level to which the leakage rate field information of the piece of data belongs is determined according to the leakage rate thresholds of each level of the corresponding valve, and the sealing level field information is added to the piece of data to obtain the second data sequence;

[0090] Nuclear power plant valves are divided into two categories: non-check valves and check valves;

[0091] When the nuclear power plant valve is a non-check valve and the test medium is liquid, the maximum allowable leakage of the nuclear power plant valve = 1.4 × DN × the number of sealing surfaces of the nuclear power plant valve;

[0092] When the nuclear power plant valve is a non-check valve and the test medium is gas, the maximum allowable leakage of the nuclear power plant valve = 120 × DN × the number of sealing surfaces of the nuclear power plant valve;

[0093] When the nuclear power plant valve is a check valve and the test medium is liquid, the maximum allowable leakage of the nuclear power plant valve = 2.8 × DN;

[0094] When the nuclear power plant valve is a check valve and the test medium is gas, the maximum allowable leakage of the nuclear power plant valve = 480 × DN;

[0095] The number of sealing pairs of nuclear power plant valves refers to the number of sealing pairs that the nuclear power plant valves themselves use to seal; DN refers to the nominal diameter of the nuclear power plant valves;

[0096] The upper limit of the leakage rate threshold of each level of nuclear power plant valves = (the level / 5)*the maximum allowable leakage rate of nuclear power plant valves.

[0097] As an example, in this embodiment, the test medium of the gate valve with the equipment code 1eas007vb is gas, the DN is 350, the number of sealing surfaces is 2, the maximum allowable leakage rate is 84000mL / h, the upper limit of the level 1 leakage rate threshold is 16800mL / h, the upper limit of the level 2 leakage rate threshold is 33600mL / h, the upper limit of the level 3 leakage rate threshold is 50400mL / h, the upper limit of the level 4 leakage rate threshold is 67200mL / h, the upper limit of the level 5 leakage rate threshold is 84000mL / h, and the upper limit of the level 6 leakage rate threshold is 50000mL / h. 0mL / h; the test medium of the gate valve with equipment code 1eas008vb is gas, DN is 350, the number of sealing surfaces is 2, the maximum allowable leakage rate is 84000mL / h, the upper limit of the level 1 leakage rate threshold is 16800mL / h, the upper limit of the level 2 leakage rate threshold is 33600mL / h, the upper limit of the level 3 leakage rate threshold is 50400mL / h, the upper limit of the level 4 leakage rate threshold is 67200mL / h, the upper limit of the level 5 leakage rate threshold is 84000mL / h, and the upper limit of the level 6 leakage rate threshold is 500000mL / h.

[0098] As an example, the second data sequence is shown in Table 2.

[0099] Table 2 Second data sequence

[0100]

[0101]

[0102] In this embodiment, in S1013, data processing is performed on the data in the second data sequence to obtain a data sequence {X(n)} of the same type of valves, including the following steps:

[0103] According to engineering experience, the sealing level of nuclear power plant valves will not significantly reverse, and the data with a difference of 2 or more between the sealing level of the same valve in the second data sequence and the previous refueling cycle are deleted as invalid data to obtain the third data sequence;

[0104] Then, the data in the third data sequence is divided according to the valve type field information, and the data with the same valve type field information constitutes a data sequence;

[0105] In the data sequence consisting of data with the same valve type field information, the data with the same device code field information are arranged in chronological order, and finally all the data are sorted to obtain the data sequence {X(n)} of the valve type.

[0106] As an example, the data sequence ﹛X(n)﹜ of the same type of valves is shown in Table 3.

[0107] Table 3 Data sequence of valves of the same type﹛X(n)﹜

[0108]

[0109] In this embodiment, in S1014, one-step state transition field information is added to the data in the data sequence {X(n)} of the same type of valves to obtain one-step state transition data of the same type of valves, including the following steps:

[0110] Calculate the one-step state transition field information of the same valve data in the data sequence ﹛X(n)﹜ of the same type of valves, and exclude the one-step state transition field information caused by external human factors (maintenance activities), and obtain the one-step state transition data of the same type of valves;

[0111] The one-step state transfer field information of the same valve data is the change in the sealing level of the same valve after a material replacement cycle.

[0112] As an example, the one-step state transfer data of the same type of valve is shown in Table 4.

[0113] Table 4 One-step state transfer data of the same type of valve

[0114]

[0115] In this embodiment, in S102, based on the one-step state transition data of the same type of valves, a one-step state transition frequency matrix F of the same type of valves is constructed, including the following steps:

[0116] According to the one-step state transfer data of the same type of valve, the frequency of the same type of valve's sealing level changing from j to k after a material replacement cycle is counted respectively, and the one-step state transfer frequency data F of the same type of valve is obtained. jk; j and k are both one of 1, 2, 3, 4, 5, 6;

[0117] According to the one-step state transfer frequency data F of the same type of valve jk , construct the one-step state transition frequency matrix F of the same type of valve:

[0118]

[0119] As an example, the frequency data F of one-step state transition of the same type of valve is jk See Table 5.

[0120] Table 5 One-step state transfer frequency data F of the same type of valve jk

[0121]

[0122] In this embodiment, in S103, the state transition probability matrix P of valves of the same type is calculated according to the one-step state transition frequency matrix F of valves of the same type:

[0123]

[0124] P jk is the state transition probability data of the same type of valve, which is calculated by the probability of the sealing level of the same type of valve transferring from j to k; j and k are both one of 1, 2, 3, 4, 5, and 6;

[0125]

[0126] In this embodiment, in S104, according to the state transition probability matrix P of the same type of valve, the state transition probability matrix P of the same type of valve within x material replacement cycles is calculated by matrix multiplication. x :

[0127] P x =P x-1 *P

[0128]

[0129] x is a natural number greater than or equal to 1.

[0130] In some embodiments, x takes the value of 20.

[0131] In this embodiment, in S105, according to the state transition probability matrix P of the same type of valve in x times of material replacement cycle x , we can get the life prediction table of the same type of valve with initial sealing level j and x refueling cycles:

[0132]

[0133] In this embodiment, in S106, according to the life prediction table of the same type of valves with initial sealing level of j level and x refueling cycles, the life of the same type of valves with initial sealing level of j level and x refueling cycles is predicted, including the following steps:

[0134] For the same type of valve, the initial sealing level is level j. From the first to the xth refueling cycle, the number of refueling cycles when the probability of the sealing level state transitioning to level 6 is the largest is the predicted life of the valve of this type.

[0135] For the same type of valve with initial sealing level of j from the 1st to the xth refueling cycle, the number of refueling cycles when the sum of the probabilities of the sealing level status transitioning to level 1-5 is greater than or equal to 50% is the predicted median life of the valve of this type;

[0136] For the same type of valve with initial sealing level j from the 1st to the xth refueling cycle, the number of refueling cycles when the sum of the probabilities of the sealing level state transitioning to level 1-5 is greater than or equal to 36.8% is the predicted characteristic life of this type of valve.

[0137] The method for predicting the sealing life of nuclear power plant valves proposed in this embodiment realizes the prediction of the sealing life of nuclear power plant valves with different initial sealing levels, and provides basic data support for subsequent preventive maintenance optimization, predictive maintenance and other work.

[0138] refer to Figure 2 As an implementation of the above method, the present invention provides an embodiment of a device for predicting the life of valve seals in a nuclear power plant. The device embodiment corresponds to the embodiment of the above method, and the device can be specifically applied to various electronic devices.

[0139] The nuclear power plant valve seal life prediction device described in this embodiment includes:

[0140] The first module 201 is used to obtain one-step state transfer data of valves of the same type in a nuclear power plant;

[0141] The second module 202 is used to construct a one-step state transition frequency matrix F of the same type of valves according to the one-step state transition data of the same type of valves;

[0142] The third module 203 is used to calculate the state transition probability matrix P of the same type of valves according to the one-step state transition frequency matrix F of the same type of valves;

[0143] The fourth module 204 is used to calculate the state transition probability matrix P of the same type of valve within x material replacement cycles according to the state transition probability matrix P of the same type of valve. x ;

[0144] The fifth module 205 is used to calculate the state transition probability matrix P of the same type of valve within x refueling cycles. x , get the life prediction table of the same type of valve with initial sealing level j and x refueling cycles;

[0145] The sixth module 206 is used to predict the life of the same type of valve with initial sealing level j within x refueling cycles according to the life prediction table of the same type of valve with initial sealing level j within x refueling cycles;

[0146] The first module 201 , the second module 202 , the third module 203 , the fourth module 204 , the fifth module 205 and the sixth module 206 are communicatively connected with each other.

[0147] The nuclear power plant valve seal life prediction device proposed in this embodiment realizes the seal life prediction of nuclear power plant valves with different initial sealing levels, providing basic data support for subsequent preventive maintenance optimization, predictive maintenance and other work.

[0148] As an implementation of the above method, the present invention provides an embodiment of a computer device, and the embodiment of the computer device corresponds to the embodiment of the above method.

[0149] The computer device described in this embodiment includes a memory 301, a processor 302 and a network interface 303 that are interconnected and communicated through a system bus. It should be noted that the figure only shows a computer device with components 301-303, but it should be understood that it is not required to implement all the components shown, and more or fewer components can be implemented instead. Among them, those skilled in the art can understand that the computer device here is a device that can automatically perform numerical calculations and / or information processing according to pre-set or stored instructions, and its hardware includes but is not limited to microprocessors, application-specific integrated circuits, programmable gate arrays, digital processors, embedded devices, etc.

[0150] The computer device may be a computing device such as a desktop computer, a notebook, a PDA, a cloud server, etc. The computer device may interact with a user through a keyboard, a mouse, a remote controller, a touch pad, or a voice control device.

[0151] The memory 301 includes at least one type of readable storage medium, and the readable storage medium includes flash memory, hard disk, multimedia card, card-type memory, random access memory, static random access memory, read-only memory, electrically erasable programmable read-only memory, programmable read-only memory, magnetic memory, disk, optical disk, etc. In some embodiments, the memory 301 can be an internal storage unit of the computer device, such as a hard disk or memory of the computer device. In other embodiments, the memory 301 can also be an external storage device of the computer device, such as a plug-in hard disk, smart memory card, secure digital card, flash memory card, etc. equipped on the computer device. Of course, the memory 301 can also include both the internal storage unit of the computer device and its external storage device. In this embodiment, the memory 301 is generally used to store the operating system and various application software installed on the computer device, such as the computer-readable instructions of the above method, etc. In addition, the memory 301 can also be used to temporarily store various types of data that have been output or are to be output.

[0152] The processor 302 may be a central processing unit, a controller, a microcontroller, a microprocessor, or other data processing chip in some embodiments. The processor 302 is generally used to control the overall operation of the computer device. In this embodiment, the processor 302 is used to run the computer-readable instructions stored in the memory 301 or process data, such as computer-readable instructions for running the above method.

[0153] The network interface 303 may include a wireless network interface or a wired network interface. The network interface 303 is generally used to establish a communication connection between the computer device and other electronic devices.

[0154] The computer equipment proposed in this embodiment realizes the prediction of the sealing life of nuclear power plant valves with different initial sealing levels, and provides basic data support for subsequent preventive maintenance optimization, predictive maintenance and other work.

[0155] As an implementation of the above method, the present invention provides an embodiment of a computer-readable storage medium, and the embodiment of the computer-readable storage medium corresponds to the embodiment of the above method.

[0156] The computer-readable storage medium described in this embodiment stores computer-readable instructions, and the computer-readable instructions can be executed by at least one processor to enable the at least one processor to perform the steps of the above method.

[0157] The computer-readable storage medium proposed in this embodiment realizes the prediction of the sealing life of nuclear power plant valves with different initial sealing levels, and provides basic data support for subsequent preventive maintenance optimization, predictive maintenance and other work.

[0158] The above-mentioned embodiments only express several implementation methods of the present invention, and the description thereof is relatively specific and detailed, but it cannot be understood as limiting the scope of the patent of the present invention. It should be pointed out that, for ordinary technicians in this field, several variations and improvements can be made without departing from the concept of the present invention, which all belong to the protection scope of the present invention. Therefore, the protection scope of the patent of the present invention shall be subject to the attached claims.

Claims

1. A method for predicting the life of valve seals in nuclear power plants, characterized in that: The following steps are involved: S101, obtaining one-step state transfer data of valves of the same type in a nuclear power plant; S102, constructing a one-step state transition frequency matrix F of valves of the same type according to the one-step state transition data of valves of the same type; S103, calculating a state transition probability matrix P of valves of the same type according to a one-step state transition frequency matrix F of valves of the same type; S104, based on the state transition probability matrix P of the same type of valve, calculate the state transition probability matrix P of the same type of valve within x material replacement cycles x ; S105, based on the state transition probability matrix P of the same type of valve in x times of material replacement cycle x , get the life prediction table of the same type of valve with initial sealing level j and x refueling cycles; S106, predicting the life of the same type of valve with initial sealing level j within x refueling cycles according to the life prediction table of the same type of valve with initial sealing level j within x refueling cycles; j is one of 1, 2, 3, 4, 5, and 6.

2. The method for predicting the life of valve seals in nuclear power plants according to claim 1, characterized in that: In S101, obtaining one-step state transfer data of valves of the same type in a nuclear power plant includes the following steps: S1011. Collect historical sealing test data of valves in nuclear power plants to obtain a first data sequence; S1012, adding sealing level field information to the data in the first data sequence to obtain a second data sequence; S1013, performing data processing on the data in the second data sequence to obtain a data sequence {X(n)} of valves of the same type; S1014. Add one-step state transfer field information to the data in the data sequence {X(n)} of the same type of valves to obtain one-step state transfer data of the same type of valves.

3. The method for predicting the life of valve seals in nuclear power plants according to claim 2, characterized in that: In S1011, the historical sealing test data of the nuclear power plant valves are data obtained from the sealing tests conducted on each valve of the nuclear power plant during each historical refueling cycle, and the historical sealing test data of the nuclear power plant valves are collected according to one refueling cycle as one data collection interval; the data in the first data sequence includes the following field information: valve type, equipment code, leakage rate and the refueling cycle in which the test is conducted.

4. The method for predicting the life of valve seals in nuclear power plants according to claim 2, characterized in that: In S1012, the sealing level field information is added to the data in the first data sequence to obtain a second data sequence, including the following steps: According to the leakage rate threshold of each valve in the nuclear power plant, the sealing level of each valve in the nuclear power plant is evenly divided into 6 levels, among which the sealing performance of level 1 to 5 decreases in sequence, level 5 is the maximum allowable leakage rate, and level 6 is unqualified; For each piece of data in the first data sequence, the leakage rate thresholds of each level of the corresponding valve are obtained according to the device code field information, and then the sealing level to which the leakage rate field information of the piece of data belongs is determined according to the leakage rate thresholds of each level of the corresponding valve, and the sealing level field information is added to the piece of data to obtain the second data sequence; The upper limit of the leakage rate threshold of each level of nuclear power plant valves = (the level / 5)*the maximum allowable leakage rate of nuclear power plant valves.

5. The method for predicting the life of valve seals in nuclear power plants according to claim 2, characterized in that: In S1013, data in the second data sequence is processed to obtain a data sequence {X(n)} of valves of the same type, including the following steps: The data in the second data sequence whose sealing level difference between the same valve and the previous material replacement cycle is 2 or more are deleted as invalid data to obtain a third data sequence; Then, the data in the third data sequence is divided according to the valve type field information, and the data with the same valve type field information constitutes a data sequence; In the data sequence consisting of data with the same valve type field information, the data with the same device code field information are arranged in chronological order, and finally all the data are sorted to obtain the data sequence {X(n)} of the valve type.

6. The method for predicting the life of valve seals in nuclear power plants according to claim 2, characterized in that: In S1014, one-step state transition field information is added to the data in the data sequence {X(n)} of the same type of valves to obtain one-step state transition data of the same type of valves, including the following steps: Calculate the one-step state transfer field information of the same valve data in the data sequence {X(n)} of the same type of valves, and exclude the one-step state transfer field information caused by external human factors to obtain the one-step state transfer data of the same type of valves; The one-step state transfer field information of the same valve data is the change in the sealing level of the same valve after a material replacement cycle.

7. The method for predicting the life of valve seals in nuclear power plants according to claim 2, characterized in that: In S102, based on the one-step state transition data of the same type of valves, a one-step state transition frequency matrix F of the same type of valves is constructed, including the following steps: According to the one-step state transfer data of the same type of valve, the frequency of the same type of valve's sealing level changing from j to k after a material replacement cycle is counted respectively, and the one-step state transfer frequency data F of the same type of valve is obtained. jk ; j and k are both one of 1, 2, 3, 4, 5, 6; According to the one-step state transfer frequency data F of the same type of valve jk , construct the one-step state transition frequency matrix F of the same type of valve:

8. The method for predicting the life of valve seals in nuclear power plants according to claim 7, characterized in that: In S103, the state transition probability matrix P of valves of the same type is calculated according to the one-step state transition frequency matrix F of valves of the same type: P jk is the state transition probability data of the same type of valve, which is calculated by the probability of the sealing level of the same type of valve transferring from j to k; j and k are both one of 1, 2, 3, 4, 5, and 6; 9. The method for predicting the sealing life of valves in nuclear power plants according to claim 8, characterized in that: In S104, according to the state transition probability matrix P of the same type of valve, the state transition probability matrix P of the same type of valve within x material replacement cycles is calculated by matrix multiplication. x : P x =P x-1 *P x is a natural number greater than or equal to 1.

10. The method for predicting the life of valve seals in nuclear power plants according to claim 9, characterized in that: In S105, according to the state transition probability matrix P of the same type of valve in x times of material replacement cycle x , we can get the life prediction table of the same type of valve with initial sealing level j and x refueling cycles:

11. The method for predicting the life of valve seals in nuclear power plants according to claim 10, characterized in that: In S106, according to the life prediction table of the same type of valves with initial sealing level of j level within x refueling cycles, the life of the same type of valves with initial sealing level of j level within x refueling cycles is predicted, including the following steps: For the same type of valve, the initial sealing level is level j. From the first to the xth refueling cycle, the number of refueling cycles when the probability of the sealing level state transitioning to level 6 is the largest is the predicted life of the valve of this type. For the same type of valve with initial sealing level of j from the 1st to the xth refueling cycle, the number of refueling cycles when the sum of the probabilities of the sealing level status transitioning to level 1-5 is greater than or equal to 50% is the predicted median life of the valve of this type; For the same type of valve with initial sealing level j from the 1st to the xth refueling cycle, the number of refueling cycles when the sum of the probabilities of the sealing level state transitioning to level 1-5 is greater than or equal to 36.8% is the predicted characteristic life of this type of valve.

12. A device for predicting the life of valve seals in a nuclear power plant, characterized in that: include: The first module is used to obtain the one-step state transfer data of the same type of valves in the nuclear power plant; The second module is used to construct a one-step state transfer frequency matrix F of the same type of valves according to the one-step state transfer data of the same type of valves; The third module is used to calculate the state transition probability matrix P of the same type of valves according to the one-step state transition frequency matrix F of the same type of valves; The fourth module is used to calculate the state transition probability matrix P of the same type of valve within x material replacement cycles according to the state transition probability matrix P of the same type of valve. x ; The fifth module is used to calculate the state transition probability matrix P of the same type of valve within x refueling cycles. x , get the life prediction table of the same type of valve with initial sealing level j and x refueling cycles; The sixth module is used to predict the life of the same type of valve with initial sealing level j within x refueling cycles according to the life prediction table of the same type of valve with initial sealing level j within x refueling cycles; The first module, the second module, the third module, the fourth module, the fifth module and the sixth module are communicatively connected with each other.

13. A computer device comprising a memory and a processor, wherein the memory stores computer-readable instructions, characterized in that: When the processor executes the computer-readable instructions, the steps of the method for predicting the seal life of a valve in a nuclear power plant as described in any one of claims 1-11 are implemented.

14. A computer-readable storage medium having computer-readable instructions stored thereon, characterized in that: When the computer-readable instructions are executed, the steps of the method for predicting the seal life of a valve in a nuclear power plant as described in any one of claims 1 to 11 are implemented.

Images