Evaluation method and device for sealing failure of containment penetration piece of nuclear power plant, storage medium and electronic equipment

Abstract

The invention relates to a nuclear power plant containment penetration assembly sealing failure evaluation method and device, a storage medium and electronic equipment. The method comprises the steps of determining a sample space for reliability data analysis of a to-be-evaluated containment penetration assembly; analyzing the failure probability characteristics of the to-be-evaluated containment penetration assembly based on the sample space to judge whether the sealing failure of the to-be-evaluated containment penetration assembly has correlation or not; if not, evaluating the reliability of the containment penetration assembly to be evaluated based on a preset reliability data analysis method; if the to-be-evaluated containment penetration piece has the correlation, performing correlation influence range analysis to obtain a time range of the correlation influence of the to-be-evaluated containment penetration piece; and evaluating the sealing performance of the containment penetration piece to be evaluated based on the time range of the correlation influence. According to the method, the latest time of sealing failure retransmission of the containment penetration assembly can be estimated, so that the aim of accurately evaluating the sealing performance of the containment penetration assembly is fulfilled, and an inappropriate maintenance strategy is prevented from being adopted for the containment penetration assembly.

Description

Technical Field

[0001] The present invention relates to the technical field of nuclear power plant containment sealing monitoring, and more specifically to a method, device, storage medium and electronic equipment for evaluating sealing failure of a nuclear power plant containment penetration. Background Art

[0002] The containment is the third safety barrier in the safety barrier of a pressurized water reactor nuclear power plant, in addition to the fuel cladding and the primary circuit pressure boundary. Its sealing must be maintained during the operation of the unit and in the event of an accident to prevent the leakage of radioactive materials. Its sealing performance is supervised through the containment sealing test in the operation and management of nuclear power plants. The sealing performance of the mid-term containment penetration isolation valve (hereinafter referred to as the containment isolation valve) is an important component of the overall sealing of the containment.

[0003] The containment isolation valves of nuclear power plants often have high reliability, and the evaluation of the sealing performance of containment isolation valves has its own particularity. It is mainly reflected in the following aspects: Different from the qualitative judgment criteria for general equipment failure, the containment isolation valve sealing failure has a clear quantitative evaluation standard - the limit of the valve leakage rate under the temperature and pressure of the LOCA accident. Therefore, the containment isolation valve has higher sealing performance requirements and is more likely to be evaluated as a sealing failure. Ordinary maintenance treatment methods may not be able to restore the initial reliability of the faulty containment valve. Since the sealing performance of the containment isolation valve can only be detected by the leakage rate test, which can only be implemented during the overhaul of the unit, the containment isolation valve sealing failure cannot be discovered in time after it occurs. Therefore, the root cause of the sealing failure may be masked by the physical changes of the valve after the sealing failure. According to the operation practice of nuclear power plants, the vast majority of containment isolation valves have not experienced sealing failure, while the proportion of containment isolation valves that have experienced sealing failure and have failed multiple times is high.

[0004] Therefore, the reasons for the containment isolation valve sealing failure are likely to include the factor of recurrence of failure, and the commonly used equipment reliability parameter evaluation method mentioned above cannot identify this hidden danger. Therefore, when evaluating the sealing performance of the containment isolation valve, the commonly used reliability data analysis technology has defects. Summary of the invention

[0005] The technical problem to be solved by the present invention is to provide a method, device, storage medium and electronic equipment for evaluating the sealing failure of a containment penetration of a nuclear power plant in view of the problems existing in the prior art.

[0006] The technical solution adopted by the present invention to solve the technical problem is: constructing a method for evaluating the sealing failure of a nuclear power plant containment penetration, comprising the following steps:

[0007] Determine the sample space for reliability data analysis of the containment penetrations to be evaluated;

[0008] Analyzing the failure probability characteristics of the containment penetration to be evaluated based on the sample space to determine whether the sealing failure of the containment penetration to be evaluated is relevant;

[0009] If there is no correlation, the reliability of the containment penetration to be evaluated is evaluated based on a preset reliability data analysis method;

[0010] If there is correlation, then a correlation impact range analysis is performed to obtain the time range of the correlation impact of the containment penetration to be evaluated;

[0011] The sealing performance of the containment penetration to be evaluated is evaluated based on the time range affected by the correlation.

[0012] In the evaluation method for sealing failure of containment penetrations in nuclear power plants of the present invention, the sample space for determining reliability data analysis of the containment penetrations to be evaluated includes:

[0013] Obtain the sealing test results of the containment penetrations to be evaluated during the overhaul;

[0014] According to the sealing test results, historical data of sealing failure of the containment penetration to be evaluated are collected; the historical data is the sample space.

[0015] In the evaluation method for sealing failure of containment penetrations in nuclear power plants of the present invention, the analysis of the failure probability characteristics of the containment penetrations to be evaluated based on the sample space to determine whether the sealing failure of the containment penetrations to be evaluated has relevance includes:

[0016] Perform sealing failure statistics according to the sample space to obtain the actual number of failed valves that have experienced multiple sealing failures;

[0017] Predict sealing failures based on the sample space to obtain the expected number of failed valves that will fail at each failure;

[0018] A comparative analysis is performed based on the actual number of failed valves and the expected number of failed valves to determine whether the sealing failure of the containment penetration to be evaluated is relevant.

[0019] In the evaluation method for sealing failure of containment penetrations in a nuclear power plant according to the present invention, the comparative analysis based on the actual number of failed valves and the expected number of failed valves to determine whether the sealing failure of the containment penetration to be evaluated is relevant includes:

[0020] Comparing the actual number of failed valves with the expected number of failed valves;

[0021] If the actual number of failed valves is less than the expected number of failed valves, it is determined that the sealing failure is not relevant;

[0022] If the actual number of failed valves is greater than the expected number of failed valves, it is preliminarily determined that the sealing failure is correlated.

[0023] In the method for evaluating sealing failure of containment penetrations in a nuclear power plant according to the present invention, the method further comprises:

[0024] Iteratively calculate the correction coefficient to obtain the predicted value of the number of valves that have not failed;

[0025] Determining whether the predicted value of the number of non-failed valves matches the actual value of the number of non-failed valves;

[0026] If they match, the iteration stops and the sealing failure is determined to be relevant.

[0027] In the evaluation method for sealing failure of containment penetrations of nuclear power plants of the present invention, if there is correlation, then the correlation influence range analysis is performed to obtain the time range of the correlation influence of the containment penetration to be evaluated, including:

[0028] A statistical analysis is performed based on the sample space to obtain a time range of the correlation impact of the containment penetration to be evaluated.

[0029] In the method for evaluating sealing failure of containment penetrations in a nuclear power plant according to the present invention, the sealing failure estimation based on the sample space to obtain the estimated number of failed valves that will fail each time comprises:

[0030] The sealing failure is predicted based on the binomial distribution law, and the expected number of failed valves in each failure is obtained.

[0031] The present invention also provides a device for evaluating sealing failure of a containment penetration of a nuclear power plant, comprising:

[0032] A sample determination unit, used to determine a sample space for reliability data analysis of the containment penetration to be evaluated;

[0033] A correlation analysis unit, configured to analyze the failure probability characteristics of the containment penetration to be evaluated based on the sample space, so as to determine whether the sealing failure of the containment penetration to be evaluated has correlation;

[0034] A reliability evaluation unit, used for evaluating the reliability of the containment penetration to be evaluated based on a preset reliability data analysis method when there is no correlation;

[0035] A correlation impact analysis unit, used to perform correlation impact range analysis when there is correlation, and obtain a time range of correlation impact of the containment penetration to be evaluated;

[0036] A correlation influence range determining unit is used to evaluate the sealing performance of the containment penetration to be evaluated based on the time range of the correlation influence.

[0037] The present invention also provides a storage medium storing a computer program, wherein the computer program is suitable for being loaded by a processor to execute the steps of the method for evaluating sealing failure of a containment penetration of a nuclear power plant as described above.

[0038] The present invention also provides an electronic device, comprising a memory and a processor, wherein the memory stores a computer program, and the processor executes the steps of the method for evaluating sealing failure of a containment penetration of a nuclear power plant as described above by calling the computer program stored in the memory.

[0039] The evaluation method, device, storage medium and electronic device for sealing failure of containment penetrations in nuclear power plants implementing the present invention have the following beneficial effects: including: determining the sample space for reliability data analysis of the containment penetrations to be evaluated; analyzing the failure probability characteristics of the containment penetrations to be evaluated based on the sample space to determine whether the sealing failure of the containment penetrations to be evaluated has correlation; if there is no correlation, evaluating the reliability of the containment penetrations to be evaluated based on a preset reliability data analysis method; if there is correlation, performing a correlation influence range analysis to obtain the time range of correlation influence of the containment penetrations to be evaluated; evaluating the sealing performance of the containment penetrations to be evaluated based on the time range of correlation influence. The present invention can estimate the latest time of recurrence of containment penetration sealing failure, so as to achieve the purpose of accurately evaluating the sealing performance of the containment penetrations and avoid adopting inappropriate maintenance strategies for the containment penetrations. BRIEF DESCRIPTION OF THE DRAWINGS

[0040] The present invention will be further described below with reference to the accompanying drawings and embodiments, in which:

[0041] Figure 1 It is a schematic flow chart of a method for evaluating sealing failure of containment penetrations of a nuclear power plant provided by the present invention;

[0042] Figure 2 It is a logic block diagram for evaluating sealing failure of containment penetrations of a nuclear power plant provided by the present invention. DETAILED DESCRIPTION

[0043] The following will be combined with the drawings in the embodiments of the present invention to clearly and completely describe the technical solutions in the embodiments of the present invention. Obviously, the described embodiments are only part of the embodiments of the present invention, not all of the embodiments. Based on the embodiments of the present invention, all other embodiments obtained by ordinary technicians in this field without creative work are within the scope of protection of the present invention.

[0044] In order to solve the defects of the existing nuclear power plant containment isolation valve seal failure evaluation, the present invention provides a nuclear power plant containment penetration seal failure evaluation method, which can be applied to the containment isolation valve. Specifically, the present invention statistically analyzes the historical performance of all containment isolation valves in nuclear power plants, and infers the latest time when the valve may fail again after the seal failure is repaired. If the valve has not failed beyond this time, it is considered that the cause of the last valve seal failure has been eliminated.

[0045] Specifically, refer to Figure 1 The method for evaluating sealing failure of containment penetrations of a nuclear power plant provided by the present invention comprises the following steps:

[0046] Step S101: Determine a sample space for reliability data analysis of a containment penetration to be evaluated.

[0047] In an embodiment of the present invention, determining the sample space for reliability data analysis of the containment penetration to be evaluated includes: obtaining the sealing test results of the containment penetration to be evaluated performed during overhaul; based on the sealing test results, collecting historical data on sealing failures of the containment penetration to be evaluated; the historical data is the sample space.

[0048] It should be noted that the containment penetration member to be evaluated in the present invention can be applied to a containment isolation valve. Hereinafter, the containment isolation valve is used to represent the containment penetration member.

[0049] Specifically, historical data of containment isolation valve failures are collected from the sealing test results performed during overhaul, including but not limited to: nuclear power plant name, unit number, overhaul number, failed valve equipment code, penetration code, performance criteria, measured leakage rate, cycle, cause analysis, corrective action, cut-off fluid, valve type, etc.

[0050] Step S102: Analyze the failure probability characteristics of the containment penetration to be evaluated based on the sample space to determine whether the sealing failure of the containment penetration to be evaluated is relevant.

[0051] In an embodiment of the present invention, failure probability characteristics of the containment penetration to be evaluated are analyzed based on the sample space to determine whether the sealing failure of the containment penetration to be evaluated is correlated, including: performing sealing failure statistics according to the sample space to obtain the actual number of failed valves that have experienced multiple sealing failures; estimating sealing failures according to the sample space to obtain the expected number of failed valves that have each failure; and performing comparative analysis based on the actual number of failed valves and the expected number of failed valves to determine whether the sealing failure of the containment penetration to be evaluated is correlated.

[0052] Optionally, in an embodiment of the present invention, sealing failure estimation is performed based on the sample space to obtain the expected number of failed valves that occur in each failure, including: sealing failure estimation is performed based on the binomial distribution law to obtain the expected number of failed valves that occur in each failure.

[0053] Among them, a comparative analysis is performed based on the actual number of failed valves and the expected number of failed valves to determine whether the sealing failure of the containment penetration to be evaluated is relevant, including: comparing the actual number of failed valves with the expected number of failed valves; if the actual number of failed valves is less than the expected number of failed valves, it is determined that the sealing failure is not relevant; if the actual number of failed valves is greater than the expected number of failed valves, it is preliminarily determined that the sealing failure is relevant.

[0054] Furthermore, in order to verify whether the assumption of failure correlation is valid, the correction coefficient is iteratively calculated to obtain the predicted value of the number of non-failed valves; it is determined whether the predicted value of the number of non-failed valves matches the actual value of the number of non-failed valves; if they match, the iteration is stopped and it is determined that the sealing failure is correlated.

[0055] Specifically, if the sealing failure is not correlated and is an independent event, the number of valves with each failure frequency estimated based on the "binomial distribution" law is consistent with or close to the actual number of valves with each failure frequency. Otherwise, the sealing failure is considered to have correlated failure characteristics and is judged and verified.

[0056] In the embodiment of the present invention, the actual number of failed valves can be counted through historical data, and the number of expected failed valves for each failure can be estimated based on the "binomial distribution" law, based on the fact that the multiple sealing failures of a single containment isolation valve are independent events. Then the two can be compared. If the actual number of failed valves is greater than the expected number of failed valves, it can be preliminarily determined that there is correlation. The correction coefficient is further used to verify whether there is correlation.

[0057] Specifically, the correction coefficient is expressed as β, which reflects the factor of recurring failure. Correlation failure is based on the following assumption: after the valve fails for the first time, maintenance fails to eliminate the root cause of the failure, and the valve fails again after a period of time. Obviously, the first failure of the valve is an independent random failure, and subsequent failures may be another random failure, or a recurring failure with the same mechanism as the previous failure. Specifically, the following formula is satisfied:

[0058] P=P ind +P d =P ind ×(1+β) (1).

[0059] Where P is the probability of sealing failure occurring again after sealing failure; P ind is the probability of independent random seal failure; P d is the probability of reseal failure.

[0060] Regardless of the type of subsequent failure, the first failure of the valve always follows the law of independent random failure, that is, the number of valves that have not failed is the same. Therefore, β can be continuously iterated to make the predicted number of valves that will not fail the seal the same as the actual number of valves that have not failed. If the final β is a positive value, it is determined that the seal failure is correlated.

[0061] Step S103: If there is no correlation, the reliability of the containment penetration to be evaluated is evaluated based on a preset reliability data analysis method.

[0062] Optionally, in an embodiment of the present invention, the preset reliability data analysis method is a reliability data analysis method commonly used in nuclear power plants.

[0063] Step S104: If there is correlation, then a correlation influence range analysis is performed to obtain the time range of the correlation influence of the containment penetration to be evaluated.

[0064] In an embodiment of the present invention, if there is correlation, a correlation influence range analysis is performed to obtain the time range of the correlation influence of the containment penetration to be evaluated, including: performing statistical analysis based on the sample space to obtain the time range of the correlation influence of the containment penetration to be evaluated.

[0065] Step S105: Evaluate the sealing performance of the containment penetration to be evaluated based on the time range of correlation influence.

[0066] In the embodiment of the present invention, the time range affected by the correlation is the sealing performance evaluation standard of the containment isolation valve to be evaluated. For example, if the containment isolation valve to be evaluated does not fail in sealing within the time range affected by the correlation, it is considered that the root cause of the last failure of the containment isolation valve to be evaluated has been eliminated, and the random failure law is followed.

[0067] The following is an example of a specific application. Take the containment isolation valve sealing test results of a pressurized water reactor nuclear power plant in the past 20 years as an example. During this period, the nuclear power plant carried out 29 overhauls, and the valve leakage rate exceeded the performance criteria specified in the test procedure 68 times. The sealing performance of the containment isolation valve with a sealing test cycle of "one refueling cycle" (1C) is evaluated. The specific steps are as follows:

[0068] (1) The sample space of this study was determined based on the following three screening criteria.

[0069] a. The sealing test cycle is "1C";

[0070] b. The valve belongs to the containment isolation valve;

[0071] c. The valve type is electric valve, pneumatic valve, manual valve or check valve.

[0072] (2) Analyze the failure probability characteristics, that is, correlation analysis.

[0073] The statistical results of the sample show that 39 valves had 69 sealing failures in total, and the point estimation method was used to calculate the probability of containment isolation valve sealing failure (Table 1). Among them, 15 valves had multiple sealing failures, resulting in 45 sealing failure events, as shown in Table 2.

[0074] Table 1 Statistics of seal failure

[0075]

[0076] Table 2 Distribution of the number of failed valves

[0077]

[0078] Assuming that the multiple sealing failures of a single containment isolation valve are independent events, the number of valves that failed each time is estimated based on the "binomial distribution" law, see Table 3.

[0079] Table 3 Distribution of valve seal failure times (independent events)

[0080]

[0081] From the comparison between Table 2 and Table 3, it can be seen that the actual number of failed valves is greater than the expected number of failed valves. The sealing failure of the containment isolation valve is not completely an independent random event, but may have correlation characteristics.

[0082] The correction coefficient β is used for further verification. The predicted value of the number of valves that have not failed is obtained by randomly assigning β. The predicted value is continuously iterated to make the predicted value close to the actual value until the predicted number of valves that do not have sealing failure is the same as the actual number of valves that have not failed. The distribution of the number of failures of the containment isolation valves after adjustment is shown in Table 4. When β is 0.58, the estimated number of valves that have not failed can match the actual number of unsealed failures, and the β coefficients are all positive, which qualitatively verifies the hypothesis that the containment isolation valve sealing failure is correlated.

[0083] Table 4 Distribution of valve seal failure times (related events)

[0084]

[0085] (3) Analysis of the impact range of correlation.

[0086] According to historical data, 15 containment isolation valves with multiple seal failures produced a total of 45 seal failure events, including 30 related failure events. The distribution of related failure events shows that 10 events occurred in the second consecutive overhaul, 10 events occurred after one overhaul, 5 events occurred after two overhauls, 1 event occurred after three overhauls, and 2 events occurred after more than three overhauls (Table 5).

[0087] Table 5 Distribution of related failure events

[0088]

[0089] It can be seen from the number of failures that the impact of repeated failures on the correlation events that occurred during the N+4 overhaul and subsequent overhauls is very small, so the sealing failures that occurred during the N+4 overhaul and subsequent overhauls can be considered as new random failures. The distribution of failure events is analyzed again, and the following results are obtained: 15 containment isolation valves with multiple sealing failures produced a total of 45 sealing failure events, including 25 correlation failure events. Among the correlation events, 10 events occurred continuously in the second consecutive overhaul, 10 events occurred after an overhaul, and 5 events occurred after two overhauls (Table 6).

[0090] Table 6 Adjusted correlation failure event distribution

[0091]

[0092] (4) Determination of the time range of correlation impact.

[0093] From the above analysis, it can be determined that the time range of correlation influence is N+3. That is, if the containment isolation valve fails to seal and can successfully pass the next three sealing tests after the repair, it is considered that the implemented maintenance work has eliminated the root cause of the sealing failure. The subsequent sealing failure will be considered as an independent event. The law of cyclic random failure can be used to evaluate the sealing performance according to the commonly used nuclear power plant reliability data analysis method.

[0094] refer to Figure 2 , Figure 2 The present invention provides a device for evaluating sealing failure of a nuclear power plant containment penetration.

[0095] Specifically, Figure 2 As shown, the evaluation device for sealing failure of containment penetrations of a nuclear power plant includes:

[0096] The sample determination unit 201 is used to determine the sample space for reliability data analysis of the containment penetration to be evaluated.

[0097] The correlation analysis unit 202 is used to analyze the failure probability characteristics of the containment penetration to be evaluated based on the sample space to determine whether the sealing failure of the containment penetration to be evaluated has correlation.

[0098] The reliability evaluation unit 203 is used to evaluate the reliability of the containment penetration to be evaluated based on a preset reliability data analysis method when there is no correlation.

[0099] The correlation impact analysis unit 204 is used to perform correlation impact range analysis when there is correlation, and obtain the time range of the correlation impact of the containment penetration to be evaluated.

[0100] The performance evaluation unit 205 is used to evaluate the sealing performance of the containment penetration to be evaluated based on the time range of correlation influence.

[0101] Specifically, the specific coordination operation process between the various units in the evaluation device for sealing failure of nuclear power plant containment penetration components here can refer to the above-mentioned evaluation method for sealing failure of nuclear power plant containment penetration components, which will not be repeated here.

[0102] The present invention can be used to infer the latest time when a valve may fail again after its sealing failure is repaired. If the valve has not failed beyond this time, it is considered that the cause of the previous valve sealing failure has been eliminated, thereby achieving the purpose of accurately evaluating the sealing performance of the containment isolation valve of a nuclear power plant and avoiding the nuclear power plant from adopting inappropriate maintenance strategies for the containment isolation valve.

[0103] In addition, an electronic device of the present invention includes a memory and a processor; the memory is used to store a computer program; the processor is used to execute the computer program to implement a method for evaluating the sealing failure of a containment penetration of a nuclear power plant as described in any one of the above. Specifically, according to an embodiment of the present invention, the process described with reference to the flowchart above can be implemented as a computer software program. For example, an embodiment of the present invention includes a computer program product, which includes a computer program carried on a computer-readable medium, and the computer program contains a program code for executing the method shown in the flowchart. In such an embodiment, the computer program can be downloaded and installed by an electronic device and when executed, it executes the above functions defined in the method of the embodiment of the present invention. The electronic device in the present invention can be a terminal such as a notebook, a desktop, a tablet computer, a smart phone, or a server.

[0104] In addition, a storage medium of the present invention stores a computer program thereon, and when the computer program is executed by a processor, it implements any of the above evaluation methods for sealing failure of nuclear power plant containment penetrations. Specifically, it should be noted that the above storage medium of the present invention may be a computer-readable signal medium or a computer-readable storage medium or any combination of the above two. The computer-readable storage medium may be, for example, but not limited to, an electrical, magnetic, optical, electromagnetic, infrared, or semiconductor system, device or device, or any combination of the above. More specific examples of computer-readable storage media may include, but are not limited to: an electrical connection with one or more wires, a portable computer disk, a hard disk, a random access memory (RAM), a read-only memory (ROM), an erasable programmable read-only memory (EPROM or flash memory), an optical fiber, a portable compact disk read-only memory (CD-ROM), an optical storage device, a magnetic storage device, or any suitable combination of the above. In the present invention, a computer-readable storage medium may be any tangible medium containing or storing a program, which may be used by or in combination with an instruction execution system, device or device. In the present invention, a computer-readable signal medium may include a data signal propagated in a baseband or as part of a carrier wave, which carries a computer-readable program code. Such propagated data signals may take a variety of forms, including but not limited to electromagnetic signals, optical signals, or any suitable combination of the above. Computer readable signal media may also be any computer readable medium other than computer readable storage media, which may send, propagate, or transmit programs for use by or in conjunction with an instruction execution system, apparatus, or device. The program code contained on the computer readable medium may be transmitted using any suitable medium, including but not limited to: wires, optical cables, RF (radio frequency), etc., or any suitable combination of the above.

[0105] The computer-readable medium may be included in the electronic device, or may exist independently without being incorporated into the electronic device.

[0106] In this specification, each embodiment is described in a progressive manner, and each embodiment focuses on the differences from other embodiments. The same or similar parts between the embodiments can be referred to each other. For the device disclosed in the embodiment, since it corresponds to the method disclosed in the embodiment, the description is relatively simple, and the relevant parts can be referred to the method part.

[0107] Professionals may further appreciate that the units and algorithm steps of each example described in conjunction with the embodiments disclosed herein can be implemented in electronic hardware, computer software, or a combination of the two. In order to clearly illustrate the interchangeability of hardware and software, the composition and steps of each example have been generally described in the above description according to function. Whether these functions are performed in hardware or software depends on the specific application and design constraints of the technical solution. Professionals and technicians may use different methods to implement the described functions for each specific application, but such implementation should not be considered to be beyond the scope of the present invention.

[0108] The steps of the method or algorithm described in conjunction with the embodiments disclosed herein may be implemented directly using hardware, a software module executed by a processor, or a combination of the two. The software module may be placed in a random access memory (RAM), a memory, a read-only memory (ROM), an electrically programmable ROM, an electrically erasable programmable ROM, a register, a hard disk, a removable disk, a CD-ROM, or any other form of storage medium known in the art.

[0109] The above embodiments are only for illustrating the technical concept and features of the present invention, and their purpose is to enable people familiar with the technology to understand the content of the present invention and implement it accordingly, and they cannot limit the scope of protection of the present invention. All equivalent changes and modifications made to the scope of the claims of the present invention should fall within the scope of the claims of the present invention.

Claims

1. A method for evaluating sealing failure of containment penetrations in a nuclear power plant, characterized in that: The following steps are involved: Determine the sample space for reliability data analysis of the containment penetrations to be evaluated; Analyzing the failure probability characteristics of the containment penetration to be evaluated based on the sample space to determine whether the sealing failure of the containment penetration to be evaluated is relevant; If there is no correlation, the reliability of the containment penetration to be evaluated is evaluated based on a preset reliability data analysis method; If there is correlation, then a correlation impact range analysis is performed to obtain the time range of the correlation impact of the containment penetration to be evaluated; The sealing performance of the containment penetration to be evaluated is evaluated based on the time range affected by the correlation.

2. The method for evaluating sealing failure of containment penetrations in nuclear power plants according to claim 1, characterized in that: The sample space for determining the reliability data analysis of the containment penetration to be evaluated includes: Obtain the sealing test results of the containment penetrations to be evaluated during the overhaul; According to the sealing test results, historical data of sealing failure of the containment penetration to be evaluated are collected; the historical data is the sample space.

3. The method for evaluating sealing failure of containment penetrations in nuclear power plants according to claim 1, characterized in that: The analyzing the failure probability characteristics of the containment penetration to be evaluated based on the sample space to determine whether the sealing failure of the containment penetration to be evaluated has relevance includes: Perform sealing failure statistics according to the sample space to obtain the actual number of failed valves that have experienced multiple sealing failures; Predict sealing failures based on the sample space to obtain the expected number of failed valves that will fail at each failure; A comparative analysis is performed based on the actual number of failed valves and the expected number of failed valves to determine whether the sealing failure of the containment penetration to be evaluated is relevant.

4. The method for evaluating sealing failure of containment penetrations in nuclear power plants according to claim 3, characterized in that: The comparative analysis based on the actual number of failed valves and the expected number of failed valves to determine whether the sealing failure of the containment penetration to be evaluated is relevant includes: Comparing the actual number of failed valves with the expected number of failed valves; If the actual number of failed valves is less than the expected number of failed valves, it is determined that the sealing failure is not relevant; If the actual number of failed valves is greater than the expected number of failed valves, it is preliminarily determined that the sealing failure is correlated.

5. The method for evaluating sealing failure of containment penetrations in nuclear power plants according to claim 4, characterized in that: The method further comprises: Iteratively calculate the correction coefficient to obtain the predicted value of the number of valves that have not failed; Determining whether the predicted value of the number of non-failed valves matches the actual value of the number of non-failed valves; If they match, the iteration stops and the sealing failure is determined to be relevant.

6. The method for evaluating sealing failure of containment penetrations in nuclear power plants according to claim 1, characterized in that: If there is correlation, then the correlation impact range analysis is performed to obtain the time range of the correlation impact of the containment penetration to be evaluated, including: A statistical analysis is performed based on the sample space to obtain a time range of the correlation impact of the containment penetration to be evaluated.

7. The method for evaluating sealing failure of containment penetrations in nuclear power plants according to claim 3, characterized in that: The estimating of sealing failure according to the sample space to obtain the estimated number of failed valves that will fail each time includes: The sealing failure is predicted based on the binomial distribution law, and the expected number of failed valves in each failure is obtained.

8. A device for evaluating sealing failure of containment penetrations in a nuclear power plant, characterized in that: include: A sample determination unit, used to determine a sample space for reliability data analysis of the containment penetration to be evaluated; A correlation analysis unit, configured to analyze the failure probability characteristics of the containment penetration to be evaluated based on the sample space, so as to determine whether the sealing failure of the containment penetration to be evaluated has correlation; A reliability evaluation unit, used for evaluating the reliability of the containment penetration to be evaluated based on a preset reliability data analysis method when there is no correlation; A correlation impact analysis unit, used to perform correlation impact range analysis when there is correlation, and obtain a time range of correlation impact of the containment penetration to be evaluated; A correlation influence range determining unit is used to evaluate the sealing performance of the containment penetration to be evaluated based on the time range of the correlation influence.

9. A storage medium, characterized in that: The storage medium stores a computer program, and the computer program is suitable for being loaded by a processor to execute the steps of the method for evaluating sealing failure of a containment penetration of a nuclear power plant as described in any one of claims 1 to 7.

10. An electronic device, characterized in that: It comprises a memory and a processor, wherein the memory stores a computer program, and the processor executes the steps of the method for evaluating sealing failure of a containment penetration of a nuclear power plant as claimed in any one of claims 1 to 7 by calling the computer program stored in the memory.

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