Method for determining containment test period, readable storage medium and computer device

Abstract

The application discloses a method for determining a containment test period. The method comprises: obtaining historical data of test results of a containment test; and determining whether the containment test period can be extended according to the historical data of the test results of the containment test. If not, the current containment test period is maintained. If yes, a first candidate value of the containment test period is obtained according to the historical data of the test results of the containment test and acceptance criteria of a safety margin of the containment test. A second candidate value of the containment test period is obtained according to the historical data of the test results of the containment test, a reference value of a risk index and acceptance criteria of the risk index. A determined value of the containment test period is determined according to the first candidate value of the containment test period and the second candidate value of the containment test period, and the determined value of the containment test period is taken as a next containment test period.

Description

Technical Field

[0001] This invention relates to the field of nuclear power plant safety analysis, and more particularly to a method for determining containment test cycles, a readable storage medium, and a computer device. Background Technology

[0002] As the last line of defense against the release of radioactive materials into the environment, the containment vessel of a nuclear power plant is responsible for containing radioactive materials and shielding against radiation under various operating conditions. To ensure the functional requirements of the containment vessel throughout the unit's lifespan, its airtightness and structural strength should be tested and verified periodically. Currently, the periodic containment tests considered in nuclear power unit design include:

[0003] Local containment test (LLRT):

[0004] Class B testing: Determines localized leaks through specific penetrations of the containment (equipment gates, personnel gates, fuel transfer channels, electrical penetrations, etc.);

[0005] Class C test: Determine local leakage through containment isolation valves.

[0006] Integrity Test for Containment (ILRT):

[0007] Category A tests: Determine the overall leakage rate of the containment and conduct strength tests during this period.

[0008] For double containment structures, containment testing also includes the measurement requirement for the leakage rate of the outer containment. This test is mainly used to coordinate with the operation of the annular space ventilation system to maintain the negative pressure state of the annular space and limit the direct leakage of radioactive materials inside the inner containment to the outside of the containment.

[0009] Category A tests, as a key component of unit refueling and overhaul operations, occupy a significant portion of the main project timeline and consume substantial manpower and resources. The possibility of introducing adverse initiation events during these tests, leading to serious consequences, makes them a crucial breakthrough point for significantly improving unit availability and economic efficiency. Currently, the formulation of containment test cycles for in-service units in China references relevant requirements from domestic and international standards and practices. Specifically, the first Category A test is conducted during the first or second reactor shutdown for refueling, and thereafter, tests are conducted no more than once every 10 years. There are specific requirements for the frequency of Category B / C tests, such as recording pressure gauge readings for electrical penetrations at least monthly, and ensuring that the interval between two isolation valve tests does not exceed two years.

[0010] However, when the nuclear power plant is operating stably and the containment is in good condition, there may be situations where containment testing is not required, but it must be conducted according to a fixed containment testing cycle. Therefore, the fixed containment testing cycle makes containment testing inflexible and may lead to higher total costs for the nuclear power plant, which is not conducive to improving the economics of nuclear power. Summary of the Invention

[0011] The technical problem this invention aims to solve is that a fixed containment test cycle leads to a lack of flexibility in containment testing and may result in high operation and maintenance costs for nuclear power plants, hindering the improvement of nuclear power's economics. To address the aforementioned shortcomings of existing technologies, this invention aims to provide a method, a readable storage medium, and a computer device for determining the containment test cycle. By dynamically predicting test results based on historical and real-time acquired data from containment tests, and determining the containment test cycle based on these results and acceptance criteria, this invention increases the flexibility of containment testing, reduces the operation and maintenance costs of nuclear power plants, and improves the economics of nuclear power.

[0012] On one hand, the present invention provides a method for determining the containment test cycle, comprising: acquiring historical data of containment test results; obtaining a first candidate value for the containment test cycle using a regression prediction method based on the historical data of containment test results and the acceptance criteria for the safety margin of the containment test; obtaining a second candidate value for the containment test cycle based on the historical data of containment test results and the acceptance criteria for a first risk indicator; the first risk indicator includes the frequency of early large-scale radioactive release and the probability of containment condition failure; and determining a finalized value for the containment test cycle based on the first candidate value and the second candidate value, and using the finalized value for the containment test cycle as the next containment test cycle.

[0013] Specifically, historical data on the test results of containment tests are obtained, including: obtaining historical data on the test results of containment tests; and determining whether to extend the containment test cycle based on the historical data on the test results of containment tests.

[0014] Specifically, historical data on containment test results is obtained, including historical data on the results of two consecutive containment tests. Based on this historical data, a determination is made as to whether to extend the containment test cycle, including determining whether the historical data on the results of two consecutive containment tests meet the acceptance criteria for the safety margin of the containment test. If yes, the containment test cycle is extended. If not, the containment test cycle is not extended.

[0015] Specifically, based on historical data of containment test results and acceptance criteria for the safety margin of containment tests, a first candidate value for the containment test cycle is obtained through regression prediction. This includes: setting a data threshold for the containment test results based on the acceptance criteria for the safety margin of containment tests; obtaining an aging correction factor for the containment based on historical data of the containment test results, and obtaining predicted results for the containment test using regression prediction based on the aging correction factor; the predicted results for the containment test include the service time of the containment and predicted data for the test results of the containment test corresponding to the service time of the containment. Furthermore, based on the data threshold of the containment test results, a first predicted data point is selected from the predicted data of the test results of the containment test corresponding to the service time of the containment, and the time interval between the service time of the containment corresponding to the first predicted data and the time of the last containment test is determined as the first candidate value for the containment test cycle. The first predicted data point is less than the data threshold of the containment test results.

[0016] Specifically, based on historical data of containment test results and the acceptance criteria for the first risk indicator, a second candidate value for the containment test cycle is obtained. This includes: setting a threshold for the increment of the first risk indicator in the containment test according to the acceptance criteria; obtaining a baseline value for the second risk indicator using statistical methods or probabilistic safety analysis methods based on historical data of the containment test results; and determining the second candidate value for the containment test cycle based on the baseline value of the second risk indicator and the threshold for the increment of the first risk indicator. The second risk indicator includes the core damage frequency, the frequency of large-scale radioactive release, and the probability of excessive risk leakage.

[0017] Specifically, based on the baseline value of the second risk indicator and the threshold of the increment of the first risk indicator, a second candidate value for the containment test cycle is determined, including: obtaining a third candidate value for the containment test cycle based on the baseline value of the second risk indicator, the threshold of the increment of the early large-scale radioactive release frequency, the baseline value of the probability of excessive risk leakage, and the current containment test cycle; obtaining a fourth candidate value for the containment test cycle based on the baseline value of the core damage frequency and the threshold of the increment of the containment condition failure probability; and obtaining a second candidate value for the containment test cycle based on the third and fourth candidate values ​​of the containment test cycle; the second candidate value for the containment test cycle is the minimum of the third and fourth candidate values ​​of the containment test cycle.

[0018] Specifically, the determined value of the containment test cycle is the minimum value between the first candidate value and the second candidate value of the containment test cycle.

[0019] Specifically, the method also includes: real-time acquisition of containment temperature, containment pressure, containment leakage rate, and penetration leakage rate monitoring results; setting early warning and alarm parameters based on the real-time monitoring results of containment temperature, containment pressure, containment leakage rate, and penetration leakage rate; and taking emergency response measures when an early warning or alarm occurs.

[0020] Specifically, this also includes: re-determining the value of the containment test cycle when emergency response measures are taken in the event of a warning or alarm.

[0021] Specifically, this also includes: adding multiple visual inspections and multiple prestressed steel strand monitoring sessions between the current containment test and the next containment test. If the visual inspection results are unsatisfactory, corrective actions will be taken until the acceptance criteria are met. Furthermore, the pressure-bearing performance will be verified based on the prestressed steel strand monitoring results; if the requirements are met, the determined value of the containment test cycle will be used as the next containment test cycle; if not, the current containment test cycle will be maintained.

[0022] In a second aspect, the present invention provides a computer device, including a memory and a processor, wherein the memory stores a computer program, and the processor executes the computer program to implement the above-described method for determining the containment test cycle.

[0023] Thirdly, the present invention provides a computer-readable storage medium having a computer program stored thereon, characterized in that, when the computer program is executed by a processor, the processor executes the above-described method for determining the containment test cycle.

[0024] The beneficial effects of the present invention include: the method for determining the containment test cycle provided by the present invention can dynamically predict the test results based on historical test data and real-time collected data of the containment test, and manage the containment test cycle according to the test results and acceptance criteria, thereby improving the flexibility of containment testing and being applicable to various types of nuclear power plants, which helps to reduce the operation and maintenance costs of nuclear power plants and improve the economics of nuclear power. Attached Figure Description

[0025] Figure 1 This is a flowchart of a method for determining the containment test cycle in an embodiment of the present invention;

[0026] Figure 2 A flowchart of another method for determining the containment test cycle in an embodiment of the present invention;

[0027] Figure 3 A flowchart of another method for determining the containment test cycle in an embodiment of the present invention;

[0028] Figure 4This is a flowchart illustrating another method for determining the containment test cycle in an embodiment of the present invention;

[0029] Figure 5 This is a flowchart of another method for determining the containment test cycle in an embodiment of the present invention. Detailed Implementation

[0030] To enable those skilled in the art to better understand the technical solution of the present invention, the embodiments of the present invention will be further described in detail below with reference to the accompanying drawings.

[0031] It is understood that the specific embodiments and accompanying drawings described herein are merely for explaining the invention and are not intended to limit the invention.

[0032] It is understood that, without conflict, the various embodiments and features in the embodiments of the present invention can be combined with each other.

[0033] It is understood that, for ease of description, only the parts related to the present invention are shown in the accompanying drawings, while the parts unrelated to the present invention are not shown in the drawings.

[0034] It is understood that each unit or module involved in the embodiments of the present invention may correspond to only one entity structure, or may be composed of multiple entity structures, or multiple units or modules may be integrated into one entity structure.

[0035] It is understood that, without conflict, the functions and steps marked in the flowcharts and block diagrams of this invention may occur in a different order than that marked in the accompanying drawings.

[0036] It is understood that the flowcharts and block diagrams of this invention illustrate the possible architecture, functions, and operations of systems, apparatuses, devices, and methods according to various embodiments of this invention. Each block in the flowchart or block diagram may represent a unit, module, program segment, or code, containing executable instructions for implementing the specified function. Furthermore, each block or combination of blocks in the block diagram and flowchart can be implemented using a hardware-based system to achieve the specified function, or using a combination of hardware and computer instructions.

[0037] It is understood that the units and modules involved in the embodiments of the present invention can be implemented by software or by hardware. For example, the units and modules can be located in a processor.

[0038] To address the lack of flexibility in containment testing, reduce the operation and maintenance costs of nuclear power plants, and improve the economics of nuclear power, embodiments of the present invention provide a method for determining the containment testing cycle, such as... Figure 1 As shown, the method includes steps 101 to 104.

[0039] Step 101: Obtain historical data of the containment test results.

[0040] For example, the implementation method of step 101 may include: obtaining historical data of the test results of the containment test, and determining whether the containment test cycle can be extended based on the historical data of the test results of the containment test.

[0041] For example, historical data on containment test results may include historical data on Class A tests, Class B tests, and Class C tests conducted at the nuclear power plant. This historical data may be stored in the nuclear power plant's database.

[0042] In some embodiments, such as Figure 2 As shown, the implementation method of step 101 may include steps 201 to 202.

[0043] Step 201: Obtain historical data of the test results of two consecutive containment tests.

[0044] For example, the historical data of the test results of two consecutive containment tests in step 201 can be retrieved from the database of this nuclear power plant.

[0045] Step 202: Determine whether the historical data of the test results of two consecutive containment tests meet the acceptance criteria for the safety margin of the containment test.

[0046] If yes, proceed to step 102 if step 202 is correct. If no, proceed to step 102.

[0047] Step 202 utilizes a risk-guided decision-making approach to assess, from a deterministic perspective, whether the results of two consecutive tests meet the acceptance criteria for safety margins, thus providing a preliminary assessment of the current condition of the containment. If the current condition of the containment allows for an extension of the containment testing period, then the period can be extended. If, based on the current condition of the containment, it is not suitable to extend the containment testing period, then the current containment testing period should be maintained to avoid exceeding leakage limits due to an extended containment testing period.

[0048] Step 102: Based on the historical data of the containment test results and the acceptance criteria for the safety margin of the containment test, obtain the first candidate value of the containment test cycle through regression prediction method.

[0049] Understandably, regression prediction is based on the principle of correlation in prediction, identifying the factors that influence the prediction target, finding an approximate functional relationship between these factors and the prediction target, and then using mathematical methods to find this relationship, ultimately achieving the prediction objective. This invention can predict the trend and level of experimental results using regression prediction.

[0050] In some embodiments, such as Figure 3 As shown, the implementation method of step 102 may include steps 301 to 303.

[0051] Step 301: Based on the acceptance criteria for the safety margin of the containment test, set the data threshold for the test results of the containment test.

[0052] For example, the data thresholds for the containment test results may include data thresholds for Class A test results, Class B test results, and Class C test results. When setting the data thresholds for the containment test results, personnel may set the data thresholds based on experience, according to the acceptance criteria for the safety margin of the containment test.

[0053] Step 302: Based on historical data of containment test results, obtain the containment aging correction factor, and based on the containment aging correction factor, obtain the predicted results of the containment test using a regression prediction method. The predicted results of the containment test include the containment service time and the predicted data of the containment test results corresponding to the containment service time.

[0054] In step 302, when obtaining the predicted results of the containment test based on historical data of the containment test results, the aging factor of the containment is taken into account, which can ensure that the predicted results are closer to the actual situation.

[0055] Step 303: Based on the data threshold of the containment test results, select the first predicted number from the predicted data of the containment test results corresponding to the containment service time; the first predicted data is less than the data threshold of the containment test results, and the time interval between the containment service time corresponding to the first predicted data and the time of the last containment test is the first candidate value of the containment test cycle.

[0056] For example, the predicted results of test item S in the containment test are shown in Table 1. Taking the test object of test item S as test object O, the test result of test item S as the leakage rate of test object O, and the time interval T as the time interval between the service time of the containment and the time of the last containment test, the predicted data of the test result of test item S is the predicted data of the leakage rate of test object O.

[0057] Table 1. Predicted results of test item S in containment testing.

[0058]

[0059] Let y be the data threshold for the leakage rate of test subject O, and a < b < c < y < d. Then, in Table 1, when the time interval T is 10 years, the predicted data (a) for the leakage rate of test subject O is less than the data threshold for the leakage rate of test subject O. When the time interval T is 11 years, the predicted data (b) for the leakage rate of test subject O is less than the data threshold for the leakage rate of test subject O. When the time interval T is 12 years, the predicted data (c) for the leakage rate of test subject O is less than the data threshold for the leakage rate of test subject O. When the time interval T is 13 years, the predicted data (d) for the leakage rate of test subject O is greater than the data threshold for the leakage rate of test subject O.

[0060] Therefore, a, b, or c can be selected as the first predicted data. Correspondingly, the first candidate value for the containment test cycle can be 10 years, 11 years, or 12 years. Depending on the characteristics of the nuclear power plant, the owner can make different settings. For example, the predicted data of the data threshold of the test result second only to the containment test can be used as the first predicted data, that is, the predicted data c of the leakage rate of test object O in Table 1 can be used as the first predicted data. In this case, the first candidate value for the containment test cycle is 12 years.

[0061] Step 103: Based on the historical data of the containment test results and the acceptance criteria of the first risk indicator, obtain the second candidate value of the containment test cycle.

[0062] In step 103, the first risk indicators include the large early release frequency (LERF) and the conditional containment failure probability (CCFP).

[0063] In some embodiments, such as Figure 4 As shown, the implementation method of step 103 may include steps 401 to 403.

[0064] Step 401: Based on the acceptance criteria for risk indicators, set the threshold for the increment of the first risk indicator in the containment test.

[0065] Step 402: Based on historical data of the containment test results, obtain the baseline value of the second risk indicator through statistical methods or probabilistic safety analysis methods.

[0066] In step 402, the second risk indicators include core damage frequency (CDF), large release frequency (LRF), and the probability of excessive risk leakage.

[0067] Step 403: Determine the second candidate value of the containment test cycle based on the baseline value of the second risk indicator and the threshold of the increment of the first risk indicator.

[0068] In some embodiments, such as Figure 5 As shown, the implementation method of step 403 may include steps 501 to 503. Step 501: Obtain a third candidate value for the containment test cycle based on the baseline value of the second risk indicator, the threshold of the early large-scale radioactive release frequency increment, the baseline value of the excessive risk leakage probability, and the current containment test cycle.

[0069] For example, the early large-scale radioactive release frequency increment ΔLERF can be calculated using equation (1).

[0070] ΔLERF=LERF'-LERF0≈(CDF0-LRF0)×(Prob'-Prob0) (1)

[0071] In Equation (1), LERF' is the early mass radioactive release frequency after the containment test period is extended, LERF0 is the baseline value of the early mass radioactive release frequency, CDF0 is the baseline value of the core damage frequency, LRF0 is the baseline value of the mass radioactive release frequency, Prob' is the probability of excessive risk leakage after the containment test period is extended, and Prob0 is the baseline value of the probability of excessive risk leakage.

[0072] For example, CDF0 and LRF0 are obtained using probabilistic safety analysis (PSA) methods based on historical data of containment test results. For instance, CDF0 and LRF0 can be obtained from relevant probabilistic safety analysis results during the design or operation phases. Prob0 is then obtained using statistical methods based on historical data of containment test results; for example, the statistical method could be the Jeffreys probability of failure formula.

[0073] The ratio of Prob' to Prob0 is equal to the ratio of the extended containment test period to the current containment test period. Therefore, if the current containment test period is 10 years and the extended period is 15 years, Prob0 = 0.1, and Prob' is 0.15.

[0074] Therefore, equation (1) can be transformed into equation (2).

[0075]

[0076] In equation (2), T' is the extended containment test period, and T is the current containment test period. According to equation (2), if ΔLERF is given as the threshold of the early mass radioactive release frequency increment, the extended containment test period T' can be obtained based on the threshold of the early mass radioactive release frequency increment, which is the third candidate value of the containment test period.

[0077] Step 502: Based on the baseline value of the core damage frequency and the threshold value of the containment condition failure probability increment, obtain the fourth candidate value of the containment test cycle.

[0078] For example, the containment condition failure probability increment ΔCCFP can be calculated by equation (3).

[0079]

[0080] In Equation (3), CCFP' is the containment condition failure probability after the containment test period is extended, CCFP0 is the baseline value of the containment condition failure probability, LRF' is the frequency of large-scale radioactive release after the containment test period is extended, and CDF' is the core damage frequency after the containment test period is extended.

[0081] According to equation (3), combined with equation (2) and equation (1), if ΔCCFP is given as the threshold of the probability increment of containment condition failure, then the fourth candidate value of the containment test cycle can be obtained.

[0082] Step 503: Obtain the second candidate value of the containment test cycle based on the third candidate value and the fourth candidate value of the containment test cycle; the second candidate value of the containment test cycle is the minimum of the third candidate value and the fourth candidate value of the containment test cycle.

[0083] Understandably, in equation (3), the increment of the containment condition failure probability is functionally related to the increment of the early large-scale radioactive release frequency. However, since their thresholds are different, the third candidate value of the containment test cycle is different from the fourth candidate value of the containment test cycle. In this case, the second candidate value of the containment test cycle can be determined according to step 503.

[0084] Step 104: Determine the determined value of the containment test cycle based on the first candidate value and the second candidate value of the containment test cycle, and use the determined value of the containment test cycle as the next containment test cycle.

[0085] In some embodiments, step 104 can be implemented by determining the minimum value between a first candidate value and a second candidate value for the containment test period.

[0086] For example, if the first candidate value for the containment test period is 12 years and the second candidate value for the containment test period is 12.5 years, since the first candidate value for the containment test period is less than the second candidate value for the containment test period, the determined value for the containment test period is 12 years.

[0087] In some embodiments, a method for determining the containment test cycle provided by the present invention further includes: acquiring in real time the real-time monitoring results of containment temperature, containment pressure, containment leakage rate, and penetration leakage rate; setting early warning settings and alarm settings based on the real-time monitoring results of containment temperature, containment pressure, containment leakage rate, and penetration leakage rate; and taking emergency response measures based on the early warning settings or alarm settings.

[0088] The early warning and alarm settings may differ for different nuclear power plants or different reactor types. The following example, using a domestic power plant as an example, illustrates the early warning and alarm settings.

[0089] When the temperature of the containment dome or bottom deviates from the normal operating value, it should be monitored promptly. For example, if it exceeds the alarm value, the cause of the alarm should be investigated immediately and the alarm fault should be eliminated (for example, the alarm card of a specific power plant can be referred to).

[0090] When the containment pressure deviates from the normal operating value, it should be monitored promptly. For example, if it exceeds the alarm value, the cause of the alarm should be found immediately, the alarm fault should be eliminated, the amount of air and nitrogen in the containment should be checked, and the process of checking the containment pressure change should be recorded. If the alarm is triggered when the low-flow scavenging circuit is running, the system should be shut down.

[0091] When the containment leakage rate deviates from the normal operating value, it should be monitored promptly. For example, if it exceeds the alarm value, the control room operators should organize inspection personnel to analyze the cause of the fault and troubleshoot it.

[0092] When an online seal detection alarm occurs on the gate, contact maintenance personnel to inspect the gate, confirm the specific cause of the excessive gate leakage rate, and perform a local seal inspection if necessary. If the test result for any part fails, the seal ring at that location should be replaced.

[0093] The containment electrical penetration is installed in a sleeve pre-installed on the containment. The containment electrical penetration is filled with nitrogen gas at a certain pressure. Its sealing performance can be checked by reading the pressure change. When the leakage rate (pressure gauge reading) of the containment electrical penetration is abnormal, the cause should be identified immediately and the fault should be eliminated in time.

[0094] In some embodiments, when emergency response measures are taken based on alarm settings, the determination value of the containment test cycle is redefined. For example, in the event of a serious leak, after taking emergency response measures corresponding to the serious leak, the determination value of the containment test cycle can be redefined according to the above method to ensure that the redefined containment test cycle is more adapted to the current containment condition, thereby avoiding more serious leaks.

[0095] In some embodiments, a method for determining the containment test cycle provided by the present invention further includes: adding multiple visual inspections and multiple prestressed steel strand monitoring between the current containment test and the next containment test. If the results of the visual inspections are unsatisfactory, corrective actions are taken until the acceptance criteria are met. Additionally, the pressure-bearing performance is verified based on the prestressed steel strand monitoring results. If the requirements are met, the determined value of the containment test cycle is used as the next containment test cycle; if not, the current containment test cycle is maintained.

[0096] For example, during construction, force sensors can be installed at both ends or one end of the steel strands. These sensors can monitor the changes in force values ​​of the steel strands over time during construction and operation, thereby assessing the performance of the steel strands and the containment capacity. If the requirements are met, the determined value of the containment test cycle can be used as the next containment test cycle. If the requirements are not met, the causes can be analyzed, and the current containment test cycle can be maintained.

[0097] Furthermore, if the determined value of the containment test cycle is used as the next containment test cycle, it may lead to a significant degradation in the performance of the containment's seal or structure, or the predicted test results may significantly exceed the acceptance criteria. In such cases, measures should be taken immediately to avoid excessive containment leakage, while maintaining the current containment test cycle.

[0098] After obtaining the determined value of the containment test cycle, supplementary strategies can be given for specific cycles based on the analysis, evaluation process and results of containment test cycle optimization, and safety review documents for cycle extension schemes can be generated for information of concern in the safety review, so as to facilitate the nuclear power plant owner to complete the safety review.

[0099] The embodiments of this invention provide a method for determining the containment test cycle. This method dynamically predicts test results based on historical test data and real-time collected data, and manages the containment test cycle according to the test results and acceptance criteria. This improves the flexibility of containment testing and is applicable to various types of nuclear power plants. Furthermore, it can be extended to other important periodic tests, such as hydrostatic testing, thereby reducing the daily operation and maintenance costs of nuclear power plants. Therefore, the method for determining the containment test cycle provided by the embodiments of this invention helps reduce the operation and maintenance costs of nuclear power plants and improves the economics of nuclear power.

[0100] The embodiments of the present invention provide a method for determining the containment test cycle that focuses on the needs and key aspects of digital transformation in traditional industries. It aims to promote the rapid development of big data intelligent evaluation management in the application of periodic test management in nuclear power plants and complete the intelligent and digital transformation of the group company.

[0101] Furthermore, the method for determining the containment test cycle provided by the embodiments of the present invention is generalizable and can be used only by making adaptive modifications according to the characteristics of a specific nuclear power plant. While intelligently evaluating the containment test cycle, it can provide supplementary strategies and comparison criteria for the implementation of strategies after the containment test cycle is extended.

[0102] Furthermore, in a method for determining the containment test cycle provided by an embodiment of the present invention, a risk-guided decision-making method is used to determine whether the containment test cycle of a specific nuclear power plant is suitable for extension, and a standard risk assessment report for safety review can be output. The extension of the containment test cycle can effectively reduce the operating costs of the power plant and improve the availability of the power plant. In particular, Class A tests can shorten the critical path of major overhauls, resulting in extremely significant economic benefits.

[0103] Meanwhile, the method for determining the containment test cycle provided by the embodiments of the present invention can assess containment integrity in real time, be used for daily containment leakage rate monitoring, and can be used for life extension assessment, thereby improving the safety of nuclear power plants. By obtaining the first and second level probabilistic safety analysis models of the operation phase through the interface with the nuclear power plant risk management application platform, and by obtaining relevant operation record information through the interface with the nuclear power plant's periodic test-related systems, the periodic containment tests can be evaluated and managed more efficiently and accurately, improving work efficiency while reducing the operating costs of nuclear power plants.

[0104] Understandably, the methods provided in the embodiments of the present invention can be upgraded by improving the database, evaluation algorithms, probabilistic safety analysis models, etc. At the same time, the methods provided in the embodiments of the present invention can be updated or modified to adapt to the historical data or system configurations of different nuclear power plants.

[0105] An embodiment of the present invention provides a computer device, including a memory and a processor. The memory stores a computer program, and the processor executes the computer program to implement the steps of the method for determining the containment test cycle described in any of the above embodiments.

[0106] Embodiments of the present invention provide a computer-readable storage medium having a computer program stored thereon, characterized in that, when the computer program is executed by a processor, the processor executes the method for determining the containment test cycle as described in any of the above embodiments.

[0107] The beneficial effects of the computer device and computer-readable storage medium provided in the embodiments of the present invention can be referred to the beneficial effects of the method for determining the containment test cycle in the above embodiments, and will not be repeated here.

[0108] It is understood that the above embodiments are merely exemplary implementations used to illustrate the principles of the present invention, and the present invention is not limited thereto. For those skilled in the art, various modifications and improvements can be made without departing from the spirit and essence of the present invention, and these modifications and improvements are also considered to be within the scope of protection of the present invention.

Claims

1. A method for determining the containment test cycle, characterized in that, The method includes: Obtain historical data on the test results of containment tests; Based on the historical data of the containment test results and the acceptance criteria for the safety margin of the containment test, the first candidate value of the containment test cycle is obtained by regression prediction method. Based on historical data of the containment test results and the acceptance criteria of the first risk indicator, a second candidate value for the containment test cycle is obtained; the first risk indicator includes the frequency of early large-scale radioactive release and the probability of containment condition failure; and Based on the first candidate value and the second candidate value of the containment test cycle, a determined value of the containment test cycle is determined, and the determined value of the containment test cycle is used as the next containment test cycle.

2. The method for determining the containment test cycle according to claim 1, characterized in that, The acquisition of historical data on the test results of the containment test includes: acquiring historical data on the test results of the containment test; and determining whether to extend the containment test cycle based on the historical data on the test results of the containment test.

3. The method for determining the containment test cycle according to claim 2, characterized in that, The historical data for obtaining the test results of the containment test includes: Obtain historical data of test results from two consecutive containment tests; The step of determining whether to extend the containment test cycle based on historical data of the containment test results includes: Determine whether the historical data of the test results of the two consecutive containment tests meet the acceptance criteria for the safety margin of the containment test; If so, then the containment test period will be extended; If not, then it is determined that the containment test period will not be extended.

4. The method for determining the containment test cycle according to claim 1, characterized in that, Based on historical data of the containment test results and the acceptance criteria for the safety margin of the containment test, a first candidate value for the containment test cycle is obtained through regression prediction, including: Based on the acceptance criteria for the safety margin of containment testing, set the data thresholds for the test results of containment testing; Based on historical data from containment test results, an aging correction factor for the containment is obtained. Then, based on this aging correction factor, a regression prediction method is used to obtain the predicted results for the containment tests. The predicted results include the containment service time and predicted data for the test results corresponding to the containment service time. Based on the data threshold of the containment test results, a first predicted data is selected from the predicted data of the containment test results corresponding to the containment service time, and the time interval between the containment service time corresponding to the first predicted data and the time of the last containment test is determined as the first candidate value of the containment test cycle; the first predicted data is less than the data threshold of the containment test results.

5. The method for determining the containment test cycle according to claim 1, characterized in that, The step of obtaining a second candidate value for the containment test cycle based on historical data of the containment test results and the acceptance criteria of the first risk indicator includes: Based on the acceptance criteria for the first risk indicator, a threshold for the increment of the first risk indicator in the containment test is set. Based on historical data from the containment tests, baseline values ​​for a second risk indicator are obtained using statistical or probabilistic safety analysis methods. This second risk indicator includes the frequency of core damage, the frequency of large-scale radioactive releases, and the probability of excessive leakage. Based on the baseline value of the second risk indicator and the threshold value of the increment of the first risk indicator, a second candidate value for the containment test cycle is determined.

6. The method for determining the containment test cycle according to claim 5, characterized in that, The step of determining the second candidate value for the containment test cycle based on the baseline value of the second risk indicator and the threshold value of the increment of the first risk indicator includes: Based on the baseline value of the second risk indicator, the threshold value of the early large-scale radioactive release frequency increment, the baseline value of the excessive risk leakage probability, and the current containment test cycle, a third candidate value for the containment test cycle is obtained. Based on the baseline value of the core damage frequency and the threshold value of the containment condition failure probability increment, a fourth candidate value for the containment test cycle is obtained; and A second candidate value for the containment test cycle is obtained based on the third candidate value and the fourth candidate value of the containment test cycle; the second candidate value of the containment test cycle is the minimum value of the third candidate value and the fourth candidate value of the containment test cycle.

7. The method for determining the containment test cycle according to any one of claims 1 to 6, characterized in that, The determination value of the containment test period is the minimum value between the first candidate value and the second candidate value of the containment test period.

8. The method for determining the containment test cycle according to claim 7, characterized in that, Also includes: Real-time monitoring results of containment temperature, containment pressure, containment leakage rate, and penetration leakage rate are obtained. Based on the real-time monitoring results of the containment temperature, containment pressure, containment leakage rate, and penetration leakage rate, early warning and alarm settings are configured. as well as When an early warning or alarm is issued, emergency response measures shall be taken.

9. The method for determining the containment test cycle according to claim 8, characterized in that, Also includes: When emergency response measures are taken in the event of a warning or alarm, the determination value of the containment test cycle shall be re-established.

10. The method for determining the containment test cycle according to any one of claims 1 to 6, characterized in that, Also includes: Between the current containment test and the next containment test, multiple visual inspections and multiple prestressed steel strand monitorings will be added; If the visual inspection results are unsatisfactory, corrective actions shall be taken until the acceptance standard is met; as well as Verify whether the pressure-bearing performance meets the requirements based on the monitoring results of the prestressed steel strands; If the requirements are met, the determined value of the containment test cycle will be used as the next containment test cycle; if not, the current containment test cycle will be maintained.

11. A computer device comprising a memory and a processor, wherein the memory stores a computer program, characterized in that, When the processor executes the computer program, it implements the method for determining the containment test cycle as described in any one of claims 1 to 10.

12. A computer-readable storage medium having a computer program stored thereon, characterized in that, When the computer program is executed by a processor, the processor performs a method for determining the containment test cycle according to any one of claims 1 to 10.

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