CN115994402A - Method for determining a containment test period, readable storage medium and computer device - Google Patents
Method for determining a containment test period, readable storage medium and computer device Download PDFInfo
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Abstract
The invention discloses a method for determining a containment test period. The method comprises the following steps: acquiring historical data of a test result of a containment test; and determining whether the containment test period can be prolonged according to the historical data of the test result of the containment test. If not, the current containment test period is maintained. If yes, then: and obtaining a first candidate value of the containment test period according to the historical data of the test result of the containment test and the acceptance criterion of the safety margin of the containment test. And obtaining a second candidate value of the containment test period according to the historical data of the test result of the containment test, the reference value of the risk index and the acceptance standard of the risk index. And determining a determined value of the containment test period according to the first candidate value of the containment test period and the second candidate value of the containment test period, and taking the determined value of the containment test period as the next containment test period.
Description
Technical Field
The invention relates to the field of safety analysis of nuclear power plants, in particular to a method for determining a containment test period, a readable storage medium and computer equipment.
Background
As a final barrier to limit the release of radioactive materials to the environment, the containment vessel of a nuclear power plant assumes the safety function of containing radioactive materials and shielding radiation under various operating conditions. In order to ensure the functional requirements of the safety shell in the service life of the unit, the tightness and the structural strength of the safety shell should be tested and verified regularly in the service life. The containment periodic test considered in the design of the nuclear power unit at the present stage comprises the following steps:
containment local test (LLRT):
class B test: measuring local leaks through containment-specific penetrations (equipment gates, personnel gates, fuel transfer channels, electrical penetrations, etc.);
class C test: local leakage through the containment isolation valve was measured.
Containment integrity test (ILRT):
class a test: the overall leak rate of the containment was measured and a strength test was performed during this period.
For the double-layer containment structure, the containment test also comprises the measurement requirement of the leakage rate of the outer containment, and the test is mainly used for being matched with the operation of an annular space ventilation system so as to maintain the negative pressure state of the annular space and limit the leakage of radioactive substances in the inner containment to the outside of the containment.
The A-type test works as a key main line of the unit refueling overhaul, occupies a main line construction period, consumes a great amount of manpower and material resources, and possibly introduces unfavorable initial events in the test process to cause serious consequences, so that the A-type test becomes an important breakthrough point for greatly improving the availability and economic benefits of the unit. At present, the establishment of the safety shell test period of the domestic in-service unit refers to the relevant requirements in domestic and foreign standards and practices, namely, the first class A test is carried out when the reactor is shut down for the first time or the second time, and the first class A test is carried out no more than 10 years later; there is a certain requirement for the frequency of class B/C tests, for example, the electrical penetration should record at least 1 electrical penetration pressure gauge reading per month, the interval between two tests of the isolation valve should not exceed 2 years, etc.
However, in the case where the operation of the nuclear power plant is stable and the state of the containment remains good, there may be a case where the containment test is not required, but is performed in a fixed containment test period, and thus the fixed containment test period makes the containment test inflexible and may result in a high total cost of the nuclear power plant, which is disadvantageous in improving the economy of the nuclear power.
Disclosure of Invention
The technical problems to be solved by the invention are as follows: the fixed containment test period causes the containment test to lack flexibility, and can lead to higher operation and maintenance costs of the nuclear power plant, which is not beneficial to improving the economy of nuclear power. In order to overcome the defects in the prior art, the invention aims to provide a method, a readable storage medium and computer equipment for determining a containment test period, which dynamically predicts a test result according to historical test data and data acquired in real time of containment tests and determines the containment test period according to the test result and acceptance criteria so as to increase the flexibility of containment tests, reduce the operation and maintenance cost of a nuclear power plant and improve the economy of nuclear power.
In one aspect, the invention provides a method of determining a containment test period, comprising: historical data of test results of the containment test are obtained. And obtaining a first candidate value of the containment test period through a regression prediction method according to the historical data of the test result of the containment test and the acceptance criterion of the safety margin of the containment test. Obtaining a second candidate value of the containment test period according to historical data of test results of the containment test and acceptance criteria of the first risk index; the first risk indicator includes an early massive radioactive release frequency and a containment condition failure probability. And determining a determined value of the containment test period according to the first candidate value of the containment test period and the second candidate value of the containment test period, and taking the determined value of the containment test period as the next containment test period.
Specifically, acquiring historical data of test results of a containment test includes: acquiring historical data of a test result of a containment test; and determining whether to extend the containment test period according to historical data of test results of the containment test.
Specifically, acquiring historical data of test results of a containment test includes: historical data of test results of two continuous containment tests are obtained. Determining whether to extend the containment test period based on historical data of test results of the containment test, comprising: and judging whether the historical data of the test results of two continuous containment tests meet the acceptance criterion of the safety margin of the containment test. If yes, determining to prolong the containment test period. If not, the containment test period is determined not to be prolonged.
Specifically, according to historical data of test results of the containment test and acceptance criteria of safety margin of the containment test, a first candidate value of a containment test period is obtained through a regression prediction method, and the method comprises the following steps: and setting a data threshold of the test result of the containment test according to the acceptance criterion of the safety margin of the containment test. According to historical data of a test result of the containment test, an aging correction factor of the containment is obtained, and according to the aging correction factor of the containment, a prediction result of the containment test is obtained through a regression prediction method; the prediction results of the containment test include prediction data of containment service time and test results of the containment test corresponding to the containment service time. And selecting first prediction data from prediction data of the test result of the containment test corresponding to the service time of the containment according to the data threshold of the test result of the containment test, and determining the time interval between the service time of the containment corresponding to the first prediction data and the time of the last containment test as a first candidate value of the containment test period. The first predicted data is less than a data threshold of the test results of the containment test.
Specifically, according to the historical data of the test result of the containment test and the acceptance standard of the first risk index, obtaining a second candidate value of the containment test period comprises: and setting a threshold value of the first risk index increment of the containment test according to the acceptance standard of the first risk index. And obtaining a reference value of the second risk index through a statistical method or a probability safety analysis method according to historical data of the test result of the containment test. And determining a second candidate value of the containment test period according to the reference value of the second risk index and the threshold value of the first risk index increment. The second risk indicators include core damage frequency, bulk radioactivity release frequency, and risk of excessive risk leakage probability.
Specifically, determining a second candidate value of the containment test period according to the reference value of the second risk indicator and the threshold value of the first risk indicator increment includes: and obtaining a third candidate value of the containment test period according to the reference value of the second risk index, the threshold value of the early massive radioactivity release frequency increment, the reference value of the risk probability of excessive risk leakage and the current containment test period. And acquiring a fourth candidate value of the containment test period according to the reference value of the core damage frequency and the threshold value of the containment condition failure probability increment. And obtaining a second candidate value of the containment test period according to the third candidate value of the containment test period and the fourth candidate value of the containment test period; the second candidate of the containment test period is the minimum of the third candidate of the containment test period and the fourth candidate of the containment test period.
Specifically, the determined value of the containment test period is the minimum value of the first candidate value of the containment test period and the second candidate value of the containment test period.
Specifically, the method further comprises: and acquiring the containment temperature, containment pressure, containment leakage rate real-time monitoring result and penetration piece leakage rate monitoring result in real time. And carrying out early warning setting and alarm setting according to the containment temperature, the containment pressure, the containment leakage rate real-time monitoring result and the penetrating piece leakage rate monitoring result. And taking emergency treatment measures when early warning or alarming occurs.
Specifically, the method further comprises the following steps: and under the condition that emergency treatment measures are adopted when early warning or alarming occurs, determining values of the containment test period are determined again.
Specifically, the method further comprises the following steps: multiple visual inspections and multiple prestress steel strand monitoring were added between the current containment test and the next containment test. If the visual inspection result is not qualified, corrective action is taken until a qualification criterion is reached. Verifying whether the pressure-bearing performance meets the requirement according to the monitoring result of the prestress steel beam; if the requirements are met, taking the determined value of the containment test period as the next containment test period; if not, the current containment test period is maintained.
In a second aspect, the invention provides a computer device comprising a memory storing a computer program and a processor implementing the method of determining a safe shell test cycle as described above when the computer program is executed by the processor.
In a third aspect, the present invention provides a computer readable storage medium having a computer program stored thereon, wherein the computer program, when executed by a processor, performs the above method of determining a safe shell test period.
The beneficial effects of the invention include: the method for determining the containment test period provided by the invention can dynamically predict the test result according to the historical test data and the data acquired in real time of the containment test, manage the containment test period according to the test result and the acceptance standard, improve the flexibility of the containment test, be applicable to various nuclear power plants, be beneficial to reducing the operation and maintenance cost of the nuclear power plants and improve the economy of nuclear power.
Drawings
FIG. 1 is a flow chart of a method of determining a containment test period in an embodiment of the present invention;
FIG. 2 is a flow chart of another method of determining a containment test period in an embodiment of the present invention;
FIG. 3 is a flow chart of a method of determining a containment test period in accordance with yet another embodiment of the present invention;
FIG. 4 is a flow chart of yet another method of determining a containment test period in an embodiment of the present invention;
FIG. 5 is a flow chart of yet another method of determining a containment test period in an embodiment of the present invention.
Detailed Description
In order to make the technical scheme of the present invention better understood by those skilled in the art, the following detailed description of the embodiments of the present invention will be given with reference to the accompanying drawings.
It is to be understood that the specific embodiments and figures described herein are merely illustrative of the invention, and are not limiting of the invention.
It is to be understood that the various embodiments of the invention and the features of the embodiments may be combined with each other without conflict.
It is to be understood that only the portions relevant to the present invention are shown in the drawings for convenience of description, and the portions irrelevant to the present invention are not shown in the drawings.
It should be understood that each unit and module in the embodiments of the present invention may correspond to only one physical structure, may be formed by a plurality of physical structures, or may be integrated into one physical structure.
It will be appreciated that, without conflict, the functions and steps noted in the flowcharts and block diagrams of the present invention may occur out of the order noted in the figures.
It is to be understood that the flowcharts and block diagrams of the present invention illustrate the architecture, functionality, and operation of possible implementations of systems, apparatuses, devices, methods according to various embodiments of the present invention. Where each block in the flowchart or block diagrams may represent a unit, module, segment, code, or the like, which comprises executable instructions for implementing the specified functions. Moreover, each block or combination of blocks in the block diagrams and flowchart illustrations can be implemented by hardware-based systems that perform the specified functions, or by combinations of hardware and computer instructions.
It should be understood that the units and modules related in the embodiments of the present invention may be implemented by software, or may be implemented by hardware, for example, the units and modules may be located in a processor.
In order to improve the lack of flexibility of the containment test, the operation and maintenance cost of the nuclear power plant is reduced, and the economy of nuclear power is improved. An embodiment of the present invention provides a method of determining a containment test period, as shown in fig. 1, the method comprising steps 101 through 104.
And 101, acquiring historical data of test results of the containment test.
Illustratively, the implementation method of step 101 may include: and acquiring historical data of the test result of the containment test, and determining whether the containment test period can be prolonged according to the historical data of the test result of the containment test.
For example, the historical data of the test results of the containment test may include the historical data of the test results of the class a test, the historical data of the test results of the class B test, and the historical data of the test results of the class C test of the present nuclear power plant. The historical data may be stored in a database of the nuclear power plant.
In some embodiments, as shown in fig. 2, the implementation method of step 101 may include steps 201 to 202.
For example, the historical data of the test results of two consecutive containment tests in step 201 may be retrieved from the database of the present nuclear power plant.
And 202, judging whether historical data of test results of two continuous containment tests meet acceptance criteria of safety margin of the containment tests.
According to step 202, if yes, it is determined to extend the containment test period, and step 102 is entered. If not, the containment test period is determined not to be prolonged.
Step 202 uses a risk guidance type decision method to evaluate whether the two continuous test results meet the acceptance criterion of the safety margin from the aspect of decision theory, so as to perform preliminary evaluation on the current situation of the safety shell. If the current situation of the containment can be prolonged, the containment test period can be prolonged, and if the containment test period is unsuitable to be prolonged according to the current situation of the containment, the current containment test period is kept, so that the occurrence of the condition of exceeding the standard of leakage caused by the prolonged containment test period is avoided.
And 102, obtaining a first candidate value of the containment test period through a regression prediction method according to historical data of test results of the containment test and acceptance criteria of safety margin of the containment test.
It can be understood that the regression prediction is based on the correlation principle of prediction, and the factors affecting the prediction target are found out, then the approximate expression of the functional relationship between the factors and the prediction target is found out, and the purpose of prediction is finally achieved by using a mathematical method. The invention can predict the variation trend and level of the test result by a regression prediction method.
In some embodiments, as shown in fig. 3, the implementation method of step 102 may include steps 301 to 303.
Illustratively, the data threshold for the test results of the containment test may include a data threshold for the test results of a class A test, a data threshold for the test results of a class B test, and a data threshold for the test results of a class C test. When setting the data threshold of the test result of the containment test, the worker can empirically set the data threshold of the test result of the containment test according to the acceptance criterion of the safety margin of the containment test.
And 302, acquiring an aging correction factor of the containment according to historical data of test results of the containment test, and acquiring a prediction result of the containment test by a regression prediction method according to the aging correction factor of the containment. The prediction results of the containment test include prediction data of containment service time and test results of the containment test corresponding to the containment service time.
In step 302, when the prediction result of the containment test is obtained according to the historical data of the test result of the containment test, the aging factor of the containment is considered, so that the prediction result can be ensured to be closer to the real situation.
For example, as shown in table 1, the prediction result of the test item S in the containment test is the test object O, the test result of the test item S is the leakage rate of the test object O, the time interval T is the time interval between the service time of the containment and the time of the last containment test, and the prediction data of the test result of the test item S is the prediction data of the leakage rate of the test object O.
TABLE 1 prediction results of test item S in the containment test
When the data threshold value of the leakage rate of the test object O is set to y and a < b < c < y < d, the predicted data (a) of the leakage rate of the test object O is smaller than the data threshold value of the leakage rate of the test object O at the time interval T of 10 years in table 1. When the time interval T is 11 years, the predicted data (b) of the leak rate of the test object O is smaller than the data threshold of the leak rate of the test object O. At 12 years of time interval T, the predicted data (c) of the leak rate of subject O is less than the data threshold of the leak rate of subject O. At 13 years of time interval T, the predicted data (d) of the leak rate of subject O is greater than the data threshold of the leak rate of subject O.
Accordingly, a, b or c may be selected as the first prediction data according to the rule, and accordingly, the first candidate value of the containment test period may be 10 years, 11 years or 12 years. Depending on the characteristics of the nuclear power plant, the owner may set different settings, for example, taking the predicted data of the data threshold next to the test result of the containment test as the first predicted data, that is, the predicted data c of the leakage rate of the object O in table 1 as the first predicted data, where the first candidate value of the containment test period is 12 years.
And step 103, obtaining a second candidate value of the containment test period according to the historical data of the test result of the containment test and the acceptance standard of the first risk index.
In step 103, the first risk indicator includes an early massive radioactive emission frequency (large early release frequency, LERF) and a containment condition failure probability (conditional containment failure probability, CCFP).
In some embodiments, as shown in fig. 4, the implementation method of step 103 may include steps 401 to 403.
And step 401, setting a threshold value of a first risk index increment of the containment test according to the acceptance standard of the risk index.
And step 402, obtaining a reference value of the second risk index through a statistical method or a probability safety analysis method according to historical data of test results of the containment test.
In step 402, the second risk indicators include core damage frequency (core damage frequency, CDF), bulk radioactivity release frequency (large release frequency, LRF), and risk of excessive risk leakage probability.
In some embodiments, as shown in fig. 5, the implementation method of step 403 may include steps 501 to 503. And step 501, obtaining a third candidate value of the containment test period according to the reference value of the second risk index, the threshold value of the early massive radioactivity release frequency increment, the reference value of the risk probability of excessive risk leakage and the current containment test period.
Illustratively, an early number of radioactivity releasing frequency increments Δlerf can be calculated by equation (1).
ΔLERF＝LERF'-LERF0≈(CDF0-LRF0)×(Prob'-Prob0) (1)
In the formula (1), LERF 'is the early-stage large-scale radioactivity release frequency after the containment test period is prolonged, LERF0 is the reference value of the early-stage large-scale radioactivity release frequency, CDF0 is the reference value of the core damage frequency, LRF0 is the reference value of the large-scale radioactivity release frequency, prob' is the risk of excessive risk leakage after the containment test period is prolonged, and Prob0 is the reference value of the risk of excessive risk leakage.
Illustratively, CDF0 and LRF0 are obtained by a probabilistic safety analysis (Probabilistic Safety Analysis, PSA) method from historical data of test results of containment tests. For example, CDF0 and LRF0 may be obtained from the probabilistic security analysis correlation results of the design phase or the operational phase. Prob0 is obtained by a statistical method according to historical data of test results of the containment test, for example, the statistical method can be Jeffreys failure probability formula.
The ratio of Prob 'to Prob0 is equal to the ratio of the extended containment test period to the current containment test period, then if the current containment test period is 10 years, the extended period is 15 years, prob0=0.1, and Prob' is 0.15.
Thus, formula (1) can be converted into formula (2).
In the formula (2), T' is an extended containment test period, and T is a current containment test period. If Δlerf is given as the threshold value of the early-stage large-amount radioactivity release frequency increment according to the formula (2), the extended containment test period T', that is, the third candidate value of the containment test period, can be obtained from the threshold value of the early-stage large-amount radioactivity release frequency increment.
Illustratively, the containment condition failure probability delta Δccfp may be calculated by equation (3).
In the formula (3), CCFP ' is the containment condition failure probability after the containment test period is prolonged, CCFP0 is a reference value of the containment condition failure probability, LRF ' is a large amount of radioactive release frequency after the containment test period is prolonged, and CDF ' is the core damage frequency after the containment test period is prolonged.
According to equation (3), in combination with equation (2) and equation (1), if Δccfp is given as the threshold value of the containment condition failure probability increment, a fourth candidate value of the containment test period can be obtained.
It will be appreciated that in equation (3), the containment condition failure probability increase is a function of the early bulk radioactivity release frequency increase, but because of the different thresholds, the third candidate for the containment test period is different from the fourth candidate for the containment test period. In this case, a second candidate value for the containment test period may be determined according to step 503.
And 104, determining a determined value of the containment test period according to the first candidate value of the containment test period and the second candidate value of the containment test period, and taking the determined value of the containment test period as the next containment test period.
In some embodiments, the implementation method of step 104 may be: the determined value of the containment test period is the minimum of the first candidate value of the containment test period and the second candidate value of the containment test period.
For example, if the first candidate of the containment test period is 12 years, the second candidate of the containment test period is 12.5 years, and the first candidate of the containment test period is smaller than the second candidate of the containment test period, the determined value of the containment test period is 12 years.
In some embodiments, a method of determining a containment test period provided by an embodiment of the present invention further comprises: acquiring a containment temperature, containment pressure, containment leakage rate real-time monitoring result and a penetration piece leakage rate monitoring result in real time; setting early warning setting and alarm setting according to the containment temperature, the containment pressure, the containment leak rate real-time monitoring result and the penetration piece leak rate monitoring result; and taking emergency treatment measures according to the early warning setting or the alarm setting.
For different nuclear power plants or different pile types, the early warning setting and the alarm setting can be different, and the early warning setting and the alarm setting are exemplarily described below by taking a domestic power plant as an example.
When the temperature of the dome or the bottom of the containment vessel deviates from the normal operation value, attention should be paid in time, for example, when the temperature is higher than the alarm value, the alarm reason should be immediately searched, and an alarm fault is discharged (for example, an alarm card of a specific power plant can be referred to).
When the pressure of the containment deviates from the normal operation value, timely attention should be paid, for example, when the pressure is higher than the alarm value, the alarm reason is immediately searched, the alarm fault is discharged, the air and nitrogen quantity in the containment is checked, and the pressure change process of the containment is recorded and checked; if an alarm is given while the low flow scavenging circuit is running, the system should be shut down.
When the containment leak rate deviates from the normal operating value, attention should be paid in time, for example, above an alarm value, the control room operator should organize the inspector to analyze the cause of the fault and remove the fault.
When the online seal detection alarm of the gate occurs, a maintainer is contacted to check the gate, the specific cause of the exceeding of the leakage rate of the gate is confirmed, and if necessary, the local seal check is carried out. If the detection result at a certain place is not qualified, the sealing ring at the place should be replaced.
The containment electric penetration piece is arranged in a sleeve reserved on the containment, nitrogen with certain pressure is filled in the containment electric penetration piece, the tightness of the containment electric penetration piece can be checked by reading pressure change, and when the leakage rate (reading of a pressure gauge) of the containment electric penetration piece is abnormal, the reason is immediately ascertained, and the fault is timely removed.
In some embodiments, the determined value of the containment test period is redetermined in the event that emergency treatment action is taken in accordance with the alarm setting. For example, when a serious leakage accident occurs, after emergency treatment measures corresponding to the serious leakage accident are taken, the determined value of the containment test period can be redetermined according to the method so as to ensure that the redetermined determined value of the containment test period is more suitable for the current containment situation, so that the more serious leakage accident is avoided.
In some embodiments, a method of determining a containment test period provided by an embodiment of the present invention further comprises: multiple visual inspections and multiple prestress steel strand monitoring were added between the current containment test and the next containment test. If the visual inspection result is not qualified, corrective action is taken until a qualification criterion is reached. And verifying whether the pressure-bearing performance meets the requirement according to the monitoring result of the prestress steel beam. If the requirements are met, taking the determined value of the containment test period as the next containment test period; if not, the current containment test period is maintained.
For example, in the construction process, steel beam force sensors can be installed at two ends or one end of the steel beam, so that the force value change of the steel beam along with time during construction and operation can be monitored through the sensors, the steel beam performance and the containment capacity can be judged, and if the requirements are met, the determined value of the containment test period can be used as the next containment test period. If the requirements are not met, the cause of the occurrence can be analyzed and the current containment test period can be maintained.
In addition, if the determined value of the containment test period is taken as the next containment test period, the performance of the seal or structure of the containment may be obviously degraded, or the predicted test result is obviously beyond the acceptance standard, measures should be immediately taken to avoid the situation of excessive leakage of the containment, and the current containment test period is maintained.
After the determined value of the containment test period is obtained, a supplementary strategy can be given for a specific period according to the analysis, evaluation process and result of the containment test period optimization, and a security evaluation file of a period extension scheme is generated for the security evaluation attention information, so that a nuclear power owner can conveniently complete security evaluation.
The method for determining the containment test period provided by the embodiment of the invention can dynamically predict the test result according to the historical test data and the real-time collected data of the containment test, manage the containment test period according to the test result and the acceptance standard, improve the flexibility of the containment test, be applicable to various nuclear power plants, and be expanded to be applied to other important periodic tests, such as a hydraulic test and the like, so as to reduce the daily operation maintenance cost of the nuclear power plant. Therefore, the method for determining the containment test period provided by the embodiment of the invention is beneficial to reducing the operation and maintenance cost of the nuclear power plant and improving the economy of nuclear power.
The method for determining the containment test period provided by the embodiment of the invention focuses on the requirements and keys of traditional industrial digital transformation, and aims to promote the rapid development of big data intelligent evaluation management in the aspect of periodic test management application of nuclear power plants and complete the intelligent and digital transformation of group companies.
Moreover, the method for determining the containment test period provided by the embodiment of the invention has popularization and can be used only by completing adaptive modification according to the characteristics of a specific nuclear power plant, and the supplementary strategy after the containment test period is prolonged and the comparison criterion of strategy implementation can be given while the containment test period is evaluated intelligently.
In addition, in the method for determining the containment test period provided by the embodiment of the invention, the risk guiding type decision method is used for judging whether the containment test period of the specific nuclear power plant has an extension condition or not, and can output a standard risk assessment report for safety assessment, so that the operation cost of the power plant can be effectively reduced, the availability of the power plant is improved, and especially, the critical path of overhaul can be shortened in the class A test, and the economic benefit is extremely remarkable.
Meanwhile, the method for determining the containment test period provided by the embodiment of the invention can evaluate the integrity of the containment in real time, is used for monitoring the daily leakage rate of the containment, can be used for prolonging the service life evaluation and the like, and improves the safety of the nuclear power plant. The primary probability safety analysis model and the secondary probability safety analysis model of the operation stage are acquired through the interfaces of the application platform for risk management of the nuclear power plant, and the related operation record information is acquired through the interfaces of the related system for periodic test of the nuclear power plant, so that the periodic test of the containment vessel can be evaluated and managed more accurately, the working efficiency is improved, and the operation cost of the nuclear power plant can be reduced.
It can be understood that the method provided by the embodiment of the invention can be updated or modified to adapt to the historical data or system configuration of different nuclear power plants through updating the database, the evaluation algorithm, the probability safety analysis model and the like.
An embodiment of the invention provides a computer device comprising a memory storing a computer program and a processor implementing the steps of the method of determining a safe shell test period described in any of the above embodiments when the computer program is executed by the processor.
An embodiment of the invention provides a computer readable storage medium having a computer program stored thereon, wherein the computer program, when executed by a processor, performs the method of determining a safe shell test period according to any of the above embodiments.
The beneficial effects of the computer device and the computer-readable storage medium provided by the embodiments of the present invention may refer to the beneficial effects of the method for determining a safe shell test period in the above embodiments, and will not be described herein.
It is to be understood that the above embodiments are merely illustrative of the application of the principles of the present invention, but not in limitation thereof. Various modifications and improvements may be made by those skilled in the art without departing from the spirit and substance of the invention, and are also considered to be within the scope of the invention.
Claims (12)
1. A method of determining a containment test period, the method comprising:
acquiring historical data of a test result of a containment test;
obtaining a first candidate value of a containment test period through a regression prediction method according to historical data of test results of the containment test and acceptance criteria of safety margin of the containment test;
obtaining a second candidate value of the containment test period according to historical data of test results of the containment test and acceptance criteria of the first risk index; the first risk indicator includes an early massive radioactivity release frequency and a containment condition failure probability; and
and determining a determined value of the containment test period according to the first candidate value of the containment test period and the second candidate value of the containment test period, and taking the determined value of the containment test period as the next containment test period.
2. The method of determining a safe shell test period according to claim 1, wherein the obtaining historical data of test results of the safe shell test comprises: acquiring historical data of a test result of a containment test; and determining whether to extend the containment test period based on historical data of test results of the containment test.
3. The method of determining a safe shell test period according to claim 2, wherein the obtaining historical data of test results of the safe shell test comprises:
acquiring historical data of test results of two continuous containment tests;
the determining whether to extend the containment test period according to the historical data of the test result of the containment test comprises:
judging whether the historical data of the test results of the two continuous containment tests meet the acceptance criterion of the safety margin of the containment test;
if yes, determining to prolong the containment test period;
if not, determining not to extend the containment test period.
4. The method for determining a safe shell test period according to claim 1, wherein the obtaining the first candidate value of the safe shell test period by a regression prediction method based on the history data of the test result of the safe shell test and the acceptance criterion of the safety margin of the safe shell test comprises:
setting a data threshold of a test result of the containment test according to an acceptance criterion of a safety margin of the containment test;
according to historical data of a test result of a containment test, an aging correction factor of the containment is obtained, and according to the aging correction factor of the containment, a prediction result of the containment test is obtained through a regression prediction method; the prediction result of the containment test comprises containment service time and prediction data of a test result of the containment test corresponding to the containment service time; and
selecting first prediction data from prediction data of test results of the containment test corresponding to the service time of the containment according to a data threshold of the test results of the containment test, and determining a time interval between the service time of the containment corresponding to the first prediction data and the time of the last containment test as a first candidate value of a containment test period; the first predicted data is less than a data threshold of a test result of the containment test.
5. The method of determining a safe shell test period according to claim 1, wherein the obtaining a second candidate value of a safe shell test period based on historical data of test results of the safe shell test and acceptance criteria of a first risk indicator comprises:
setting a threshold value of a first risk index increment of the containment test according to an acceptance standard of the first risk index;
acquiring a reference value of a second risk index through a statistical method or a probability safety analysis method according to historical data of a test result of the containment test; the second risk indicator includes a core damage frequency, a bulk radioactivity release frequency, and an excessive risk leakage risk probability; and
and determining a second candidate value of the containment test period according to the reference value of the second risk index and the threshold value of the first risk index increment.
6. The method of determining a safe shell test period according to claim 5, wherein the determining a second candidate value of a safe shell test period based on the reference value of the second risk indicator and the threshold value of the first risk indicator increment comprises:
acquiring a third candidate value of the containment test period according to the reference value of the second risk index, the threshold value of the early massive radioactivity release frequency increment, the reference value of the risk probability of excessive risk leakage and the current containment test period;
acquiring a fourth candidate value of the containment test period according to the reference value of the core damage frequency and the threshold value of the containment condition failure probability increment; and
acquiring a second candidate value of the containment test period according to the third candidate value of the containment test period and the fourth candidate value of the containment test period; the second candidate value of the containment test period is the minimum value of the third candidate value of the containment test period and the fourth candidate value of the containment test period.
7. The method of determining a safe shell test period according to any one of claims 1 to 6, wherein the determined value of the safe shell test period is the minimum of a first candidate value of the safe shell test period and a second candidate value of the safe shell test period.
8. The method of determining a safe shell test period of claim 7, further comprising: acquiring a containment temperature, containment pressure, containment leakage rate real-time monitoring result and a penetration piece leakage rate monitoring result in real time;
performing early warning setting and alarm setting according to the containment temperature, the containment pressure, the containment leak rate real-time monitoring result and the penetration leak rate monitoring result; and
when early warning or alarming occurs, emergency treatment measures are adopted.
9. The method of determining a safe shell test period of claim 8, further comprising:
and under the condition that emergency treatment measures are adopted when early warning or alarming occurs, determining values of the containment test period are determined again.
10. The method of determining a safe shell assay period according to any one of claims 1-6, further comprising:
multiple visual inspection and multiple prestress steel beam monitoring are added between the current containment test and the next containment test;
if the visual inspection result is not qualified, taking corrective action until a qualified standard is reached; and
verifying whether the pressure-bearing performance meets the requirement according to the monitoring result of the prestress steel beam; if the requirements are met, taking the determined value of the containment test period as the next containment test period; if not, the current containment test period is maintained.
11. A computer device comprising a memory and a processor, the memory storing a computer program, characterized in that the processor implements the method of determining a safe shell test period according to any one of claims 1 to 10 when executing the computer program.
12. A computer readable storage medium, on which a computer program is stored, characterized in that the computer program, when being executed by a processor, performs the method of determining a safe shell test period according to any one of claims 1 to 10.
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