Detection method and device of pressurized water reactor containment pressure control system and storage medium

Abstract

The invention discloses a pressurized water reactor containment pressure control system detection method and device and a storage medium, and the method comprises the steps: obtaining a plurality of first accident sequences, and carrying out the accident type division of the plurality of first accident sequences, the first accident sequences belonging to the same accident type are merged according to the reactor core damage degree caused by the accident sequences, the first accident sequence with the highest reactor core damage degree or the fastest accident process corresponding to each accident type is obtained, and then effectiveness detection is carried out on the pressurized water reactor containment pressure control system; according to the method and the device, the plurality of first accident sequences are screened, the accident sequences which have different categories and have representative meanings in the same category are screened from the plurality of first accident sequences, and the effectiveness detection of the pressurized water reactor containment pressure control system is carried out only by using the screened accident sequences with the representative meanings. The workload of effectiveness detection of the pressurized water reactor containment pressure control system is reduced, and the efficiency of effectiveness detection is improved.

Description

Technical Field

[0001] The present application relates to the field of pressurized water reactor safety detection, and in particular to a detection method, device and storage medium for a pressurized water reactor containment pressure control system. Background Art

[0002] Nuclear power plant containment overpressure refers to the increase in containment temperature and pressure due to the continuous generation of decay heat, the continuous evaporation of core water, or the non-condensable gas produced by the reaction of core molten material and concrete when a serious accident occurs in a nuclear power plant. In the absence of effective heat conduction and pressure relief means, the containment pressure continues to rise until it reaches its failure pressure, resulting in containment overpressure failure, the nuclear power plant loses its third radioactive barrier, and radioactive substances are released into the environment, with extremely serious consequences.

[0003] To avoid the above situation, the new pressurized water reactor is equipped with a containment heat extraction system and a containment filtration and discharge system to extract the heat from the containment in the event of a severe accident, avoid late overpressure failure of the containment, and ensure the integrity of the containment. In order to prove the effectiveness of the containment overpressure relief measures, it is necessary to use accident sequences to test them, but there are currently a large number of accident sequences. If all of them are to be tested, the workload will be huge and the efficiency will be low. Summary of the invention

[0004] The present application aims to at least solve the technical problems existing in the prior art. To this end, the present application proposes a detection method, device and storage medium for a pressurized water reactor containment pressure control system, which can select representative accident sequences from a large number of accident sequences and improve the efficiency of effectiveness detection of the pressurized water reactor containment pressure control system.

[0005] To achieve the above-mentioned purpose, in a first aspect of an embodiment of the present application, an embodiment of the present application provides a method for detecting a pressure control system of a pressurized water reactor containment vessel, the method comprising:

[0006] Acquire a plurality of first accident sequences, where the first accident sequence refers to an accident sequence having a probability of causing damage to a pressurized water reactor core;

[0007] Classifying the multiple first accident sequences into accident types;

[0008] The first accident sequences belonging to the same accident type are merged according to the core damage degree or accident progress speed caused by the accident sequence, and the first accident sequence with the highest core damage degree or the fastest accident progress corresponding to each accident type is obtained;

[0009] Based on the first accident sequence corresponding to each accident type, which has the highest degree of core damage or the fastest accident process, the effectiveness of the pressurized water reactor containment pressure control system is detected.

[0010] The first aspect of the embodiment of the present application has the following beneficial effects:

[0011] The embodiment of the present application divides multiple first accident sequences into accident types; then, the first accident sequences belonging to the same accident type are merged according to the degree of core damage caused by the accident sequences or the speed of accident progress, so as to obtain the first accident sequence with the highest degree of core damage or the fastest accident progress corresponding to each accident type; based on the first accident sequence with the highest degree of core damage or the fastest accident progress corresponding to each accident type, the pressurized water reactor containment pressure control system is tested for effectiveness; the present embodiment screens multiple first accident sequences and can screen out accident sequences with different categories and representative significance in the same category from the multiple first accident sequences, and only uses the screened out representative accident sequences to perform effectiveness testing of the pressurized water reactor containment pressure control system, thereby reducing the workload of effectiveness testing of the pressurized water reactor containment pressure control system, thereby improving the efficiency of effectiveness testing of the pressurized water reactor containment pressure control system.

[0012] In some embodiments of the present application, the obtaining of a plurality of first accident sequences includes:

[0013] Obtain multiple accident sequences;

[0014] Determining the index value of the evaluation index of the impact of each of the accident sequences on the pressurized water reactor containment;

[0015] The plurality of first accident sequences are obtained by screening the plurality of accident sequences based on an index value of an evaluation index of an impact of each of the accident sequences on a pressurized water reactor containment.

[0016] In some embodiments of the present application, the multiple first accident sequences are obtained by screening the multiple accident sequences based on the index value of the evaluation index of the impact of each of the accident sequences on the pressurized water reactor containment, including at least one of the following:

[0017] If the index value includes a probability value of a pressurized water reactor core melt caused by the accident sequence, then selecting the accident sequence whose probability value is greater than a first threshold from the multiple accident sequences as a first accident sequence;

[0018] If the indicator value includes a first frequency value of pressurized water reactor core damage caused by the accident sequence, selecting the accident sequence whose first frequency value is greater than a second threshold value from the multiple accident sequences as a first accident sequence;

[0019] If the indicator value includes a second frequency value of radioactive release caused by the accident sequence, selecting the accident sequence whose second frequency value is greater than a third threshold value from the multiple accident sequences as the first accident sequence;

[0020] If the index value includes the contribution of the core damage frequency caused by the accident sequence, the accident sequence whose contribution is greater than a fourth threshold is selected from the multiple accident sequences as the first accident sequence.

[0021] In some embodiments of the present application, before classifying the multiple first accident sequences into accident types, the method further includes:

[0022] Eliminating some of the first accident sequences that meet the elimination conditions among the multiple first accident sequences;

[0023] The classifying the multiple first accident sequences into accident types includes:

[0024] Classifying the multiple first accident sequences after excluding some of the first accident sequences by accident type;

[0025] The elimination conditions include:

[0026] The accident sequence leading to the rupture of the pressure vessel;

[0027] Accident sequences that result in reactivity that cannot be effectively controlled;

[0028] Accident sequence resulting in failure of shutdown signal and inability to shutdown the reactor;

[0029] Accident sequences resulting in a containment bypass type.

[0030] In some embodiments of the present application, the first accident sequence is an accident sequence in which the contribution value of the damage to the core of the pressurized water reactor and the deterioration of the performance of the containment exceeds a preset threshold;

[0031] Before performing effectiveness detection on the pressurized water reactor containment pressure control system based on the first accident sequence corresponding to each accident type with the highest degree of core damage or the fastest accident progress, the method further includes:

[0032] receiving a screening operation for a plurality of second accident sequences, where the second accident sequence is an accident sequence whose contribution value to pressurized water reactor core damage and containment performance deterioration is lower than a preset threshold;

[0033] The effectiveness detection of the pressurized water reactor containment pressure control system based on the first accident sequence corresponding to each accident type with the highest degree of core damage or the fastest accident process includes:

[0034] Based on the first accident sequence corresponding to the highest degree of core damage or the fastest accident process for each accident type and the multiple second accident sequences screened by the screening operation, the effectiveness of the pressurized water reactor containment pressure control system is detected.

[0035] In some embodiments of the present application, before performing effectiveness detection on the pressurized water reactor containment pressure control system based on the first accident sequence corresponding to each accident type with the highest degree of core damage or the fastest accident progress, the method further includes:

[0036] From the first accident sequences corresponding to each accident type, the first accident sequence in which the accident progress speed is higher than the fifth threshold and the mass energy release in the containment is higher than the sixth threshold is selected as the third accident sequence;

[0037] The effectiveness detection of the pressurized water reactor containment pressure control system based on the first accident sequence corresponding to each accident type with the highest degree of core damage or the fastest accident process includes:

[0038] The effectiveness of the pressurized water reactor containment pressure control system is detected through the third accident sequence.

[0039] In some embodiments of the present application, the classifying the multiple first accident sequences into accident types includes at least one of the following:

[0040] Classifying the first accident sequences having the same initiating event into the same accident type;

[0041] Classifying the first accident sequences having a unique initiating event and the same accident process among the multiple first accident sequences into the same accident type;

[0042] Classify the first accident sequences having a unique initiating event among the multiple first accident sequences and having a similarity higher than a seventh threshold into the same accident type

[0043] To achieve the above-mentioned purpose, in a second aspect of the embodiments of the present application, the embodiments of the present application provide a detection device for a pressurized water reactor containment pressure control system, the device comprising:

[0044] An accident sequence acquisition unit, configured to acquire a plurality of first accident sequences, wherein the first accident sequence refers to an accident sequence having a probability of causing damage to the core of a pressurized water reactor;

[0045] An accident type classification unit, configured to classify the multiple first accident sequences into accident types;

[0046] An accident sequence selection unit is used to merge the first accident sequences belonging to the same accident type according to the core damage degree or accident progress speed caused by the accident sequence, and obtain the first accident sequence with the highest core damage degree or the fastest accident progress corresponding to each accident type;

[0047] The control system detection unit is used to detect the effectiveness of the pressure control system of the containment vessel of the pressurized water reactor based on the first accident sequence corresponding to each accident type with the highest degree of core damage or the fastest accident process.

[0048] To achieve the above-mentioned purpose, in a third aspect of an embodiment of the present application, an embodiment of the present application provides an electronic device, comprising at least one control processor and a memory for communicating with the at least one control processor; the memory stores instructions that can be executed by the at least one control processor, and the instructions are executed by the at least one control processor so that the at least one control processor can execute the detection method of the pressurized water reactor containment pressure control system described in the first aspect.

[0049] To achieve the above-mentioned purpose, in a fourth aspect of an embodiment of the present application, an embodiment of the present application provides a computer-readable storage medium, wherein the computer-readable storage medium stores computer-executable instructions, and the computer-executable instructions are used to enable a computer to execute the detection method for the pressurized water reactor containment pressure control system described in the first aspect. BRIEF DESCRIPTION OF THE DRAWINGS

[0050] In order to more clearly illustrate the technical solutions in the embodiments of the present application, the drawings required for use in the embodiments or related technical descriptions will be briefly introduced below. Obviously, the drawings described below are only some embodiments of the embodiments of the present application. For ordinary technicians in this field, other drawings can be obtained based on these drawings without paying creative labor.

[0051] Figure 1 It is a flow chart of an embodiment of a detection method for a pressurized water reactor containment pressure control system provided by the present application;

[0052] Figure 2 It is a structural schematic diagram of an embodiment of a detection device for a pressurized water reactor containment pressure control system provided by the present application;

[0053] Figure 3 It is a schematic diagram of the structure of an embodiment of the electronic device provided by the present application. DETAILED DESCRIPTION

[0054] The embodiments of the present application are described in detail below, and examples of the embodiments are shown in the accompanying drawings, wherein the same or similar reference numerals throughout represent the same or similar elements or elements having the same or similar functions. The embodiments described below with reference to the accompanying drawings are exemplary and are only used to explain the present application, and cannot be understood as limiting the present application.

[0055] In the description of this application, if there is a description of first, second, etc., it is only for the purpose of distinguishing technical features, and cannot be understood as indicating or implying relative importance or implicitly indicating the number of the indicated technical features or implicitly indicating the order of the indicated technical features.

[0056] In the description of the present application, it should be understood that the descriptions involving orientation, such as the orientation or positional relationship indicated as up, down, etc., are based on the orientation or positional relationship shown in the drawings, and are only for the convenience of describing the present application and simplifying the description, and do not indicate or imply that the device or element referred to must have a specific orientation, be constructed and operated in a specific orientation, and therefore should not be understood as a limitation on the present application.

[0057] Reference Figure 1 In one embodiment of the present application, a method for detecting a pressure control system of a pressurized water reactor containment vessel is provided, the method comprising the following steps S200 to S800:

[0058] Step S200: Acquire multiple first accident sequences.

[0059] Step S400: classify multiple first accident sequences into accident types.

[0060] Step S600: merging first accident sequences belonging to the same accident type according to the core damage degree or accident progress speed caused by the accident sequence, to obtain the first accident sequence with the highest core damage degree or the fastest accident progress corresponding to each accident type.

[0061] Step S800: Based on the first accident sequence with the highest degree of core damage or the fastest accident process corresponding to each accident type, the effectiveness of the pressurized water reactor containment pressure control system is detected.

[0062] In the art, there are a large number of accident sequences that lead to core damage. The purpose of this embodiment is to select typical and enveloping accident sequences (i.e., accident sequences that are enveloping through the accident process or that cause enveloping consequences) from the large number of accident sequences, and then only use the selected representative accident sequences to perform effectiveness detection of the pressurized water reactor containment pressure control system. Among them, the first accident sequence in step S200 refers to a part of the accident sequences in the large number of accident sequences, which can be directly specified or selected by a certain rule.

[0063] First, how to obtain multiple first accident sequences is introduced. In some embodiments, step S200 includes steps S210 to S230:

[0064] Step S210: Acquire multiple accident sequences.

[0065] Step S220: Determine the index value of the evaluation index of the impact of each accident sequence on the pressurized water reactor containment.

[0066] Step S230: Based on the index value of the evaluation index of each accident sequence affecting the containment of the pressurized water reactor, a plurality of first accident sequences are screened from the plurality of accident sequences.

[0067] In step S210, the multiple accident sequences may be accident sequences collected in advance. These accident sequences may be accident sequences collected during the operation cycle of the nuclear reactor, or may be accident sequences of the nuclear reactor simulated based on a nuclear reactor model. The acquisition method is not limited here.

[0068] In step S220, an evaluation system for accident sequences may be set up. The evaluation system may include a variety of evaluation indicators that affect the containment of a pressurized water reactor. Accident sequences are rated according to the indicator values ​​of the multiple evaluation indicators. The rating results may be used to assess the severity of the accident sequence or to classify it, which is not specifically limited here.

[0069] For example, an association relationship can be established between the accident sequence and the index value of the evaluation index, and then set into a table and stored in the form of key values. When using it, you only need to look up the table to determine the index value of the evaluation index that each accident sequence affects the pressurized water reactor containment.

[0070] In step S230, multiple accident sequences may be screened according to the index values. For example, multiple accident sequences may be sorted according to the index values, and multiple first accident sequences that are sorted first may be selected.

[0071] This embodiment obtains the index value of the evaluation index of the impact of each accident sequence on the pressurized water reactor containment, and can evaluate the impact degree of multiple accident sequences on the pressurized water reactor containment through the index value, so as to facilitate the selection of multiple first accident sequences associated with the impact degree from multiple accident sequences, thereby improving the efficiency of subsequent screening of accident sequences.

[0072] It should be noted that the above-mentioned acquisition of multiple first accident sequences may also be to directly use the accident sequences collected in the above-mentioned step S210 as the above-mentioned multiple first accident sequences, without executing the above-mentioned steps S220 and S230.

[0073] In some embodiments of the present application, the index value of the evaluation index of the impact of each accident sequence on the pressurized water reactor containment in the above step S230 is used to screen multiple accident sequences to obtain multiple first accident sequences, including at least one of the following:

[0074] If the index value includes a probability value of a pressurized water reactor core melt caused by an accident sequence, an accident sequence having a probability value greater than a first threshold value is selected from the multiple accident sequences as a first accident sequence;

[0075] If the index value includes a first frequency value of pressurized water reactor core damage caused by the accident sequence, an accident sequence having a first frequency value greater than a second threshold value is selected from the multiple accident sequences as a first accident sequence;

[0076] If the index value includes a second frequency value of radioactive release caused by the accident sequence, an accident sequence whose second frequency value is greater than a third threshold value is selected from the multiple accident sequences as a first accident sequence;

[0077] If the index value includes the contribution of the core damage frequency caused by the accident sequence, an accident sequence whose contribution is greater than a fourth threshold is selected from the multiple accident sequences as the first accident sequence.

[0078] In the above four situations, the probability value of pressurized water reactor core melting, the first frequency value of pressurized water reactor core damage, the second frequency value of radioactive release and the contribution of core damage frequency can be obtained by statistical analysis during the operation of the nuclear reactor; or by simulating each accident sequence in the simulation model. Among them, the first threshold, the second threshold, the third threshold and the fourth threshold can be set according to the reactor operation experience, and no specific limitation is made here.

[0079] This embodiment is provided with an index value for obtaining an evaluation index of the impact of each accident sequence on the pressurized water reactor containment. The index value can be used to evaluate the four ways in which multiple accident sequences have an impact on the pressurized water reactor containment. Multiple first accident sequences can be screened in different ways. For example, when one way cannot be used for screening, other ways can be used for screening, thereby improving the flexibility and convenience of screening multiple first accident sequences.

[0080] In the above step S400, the multiple first accident sequences are classified into accident types, that is, the multiple first accident sequences are classified. In some embodiments of the present application, the multiple first accident sequences are classified into accident types including at least one of the following:

[0081] Classify the first accident sequences with the same initiating event into the same accident type;

[0082] Classify the first accident sequences with a unique initiating event and the same accident process among multiple first accident sequences into the same accident type;

[0083] The first accident sequences having a unique initiating event and having a similarity higher than a seventh threshold among the plurality of first accident sequences are classified into the same accident type.

[0084] This embodiment sets three types of accidents. The first case corresponds to an accident type that means accident sequences with the same initiating event are classified into the same category. For example, accident sequence 1 to accident sequence 8, where the initiating events of accident sequence 1 and accident sequence 2 are "power failure of the entire plant", then their initiating events are the same, and accident sequence 1 and accident sequence 2 are classified into the same category; accident sequence 3 and accident sequence 4 have the same initiating events, which are different from accident sequence 1 and accident sequence 2, and accident sequence 3 and accident sequence 4 are classified into the same category.

[0085] The initiating event refers to the first event that leads to the accident. For example, the core coolant cannot be replenished due to a power outage in the entire plant, which eventually leads to the core exposure and a series of other serious consequences. The "power outage in the entire plant" here is the initiating event.

[0086] The second situation is to divide the remaining accident sequences in the above situation. For example, accident sequence 5 and accident sequence 6 both have unique initiating events, that is, the initiating events of accident sequence 5 and accident sequence 6 are different, and the initiating events of accident sequence 5, accident sequence 6 and other accident sequences are also different, but the accident process of accident sequence 5 and accident sequence 6 is the same, so they are divided into the same category. In addition, in this field, there is a clear definition of the accident process, which will not be repeated here.

[0087] The third case is to divide the remaining accident sequences of the first case. For example, accident sequence 7 and accident sequence 8 both have unique initiating events, and the similarity between accident sequence 7 and accident sequence 8 is higher than the threshold, then accident sequence 7 and accident sequence 8 are divided into the same category.

[0088] Whether the two accident sequences are similar is determined by determining the similarity between each two accident sequences. The calculation method for calculating the similarity between accident sequences may be set in advance, and no specific limitation is made here.

[0089] This embodiment sets a plurality of accident types, and by classifying a plurality of first accident sequences into accident types, a plurality of first accident sequences belonging to the same accident type can be screened based on the accident type, thereby improving the efficiency of subsequent accident sequence screening.

[0090] In the above step S600, the first accident sequences belonging to the same accident type are merged according to the core damage degree caused by the accident sequences, and the first accident sequence finally selected is the accident sequence with the highest core damage degree or the fastest accident progress among the same type, that is, the accident sequence with an envelope in the accident progress speed or core damage degree (that is, the accident sequence with a fast progress envelopes the accident sequence with a slow progress, or the accident sequence with a high core damage degree envelopes the accident sequence with a low damage degree) among the same type of accident sequences.

[0091] The merging process here is to use accident sequences with high accident severity (i.e., high core damage) to envelop accident sequences with low severity, or accident sequences with fast accident progression to envelop slow accident sequences. For example, in the first accident type, there are 10 first accident sequences, i.e., first accident sequence 1 to first accident sequence 10. Then, the first accident sequence 1 with the highest degree of core damage can be enveloping the other 9 first accident sequences, and finally, only the first accident sequence 1 is retained among the first accident sequences 1 to 10 in this type. Alternatively, in the second accident type, there are the same number of first accident sequences, and the first accident sequence 3 with the fastest accident progression can be enveloping the other 9 first accident sequences.

[0092] In the above step S800, by selecting the first accident sequence with the highest degree of core damage or the fastest accident progress, the effectiveness of the pressurized water reactor containment pressure control system is tested, which can reduce the workload of the effectiveness test of the pressurized water reactor containment pressure control system, thereby improving the efficiency of the effectiveness test of the pressurized water reactor containment pressure control system.

[0093] It should be noted that, usually, a pressurized water reactor containment pressure control system (which may be a containment heat extraction system, a containment filtration and exhaust system, etc.) has several built-in processing programs, the purpose of which is to extract the heat in the containment under severe accidents, avoid overpressure failure of the containment, and ensure the integrity of the containment; by selecting accident sequences to detect them, parameters corresponding to different accident sequences can be set in the pressurized water reactor containment pressure control system, and then the pressurized water reactor containment pressure control system runs automatically to detect the reliability of the processing programs therein.

[0094] In some embodiments of the present application, before step S400 classifies the multiple first accident sequences into accident types, the method further includes step S310:

[0095] Step S310: Eliminate some of the first accident sequences that meet the elimination conditions among the multiple first accident sequences.

[0096] The above step S400 may include:

[0097] Step S410, classifying the multiple first accident sequences after removing some first accident sequences into accident types;

[0098] Among them, the exclusion conditions include: accident sequences causing pressure vessel rupture, accident sequences causing reactivity to be unable to be effectively controlled, accident sequences causing shutdown signals to fail and failure to shut down the reactor, and accident sequences causing containment bypass.

[0099] Because the above-mentioned accident sequences may cause the safety mitigation capability of the pressurized water reactor containment pressure control system to be exceeded, by eliminating the above-mentioned four accident sequences and filtering out accident sequences that exceed the safety mitigation capability of the pressurized water reactor containment pressure control system, interference with subsequent detection can be avoided.

[0100] It should be noted that, instead of eliminating the accident sequences, the selected multiple first accident sequences may be directly classified into types and then eliminated before the final effectiveness test of the system. Alternatively, if these accident sequences are retained until the end, the effectiveness test of the system may be directly performed, and the test results (the results obtained by testing the above accident sequences) may be manually processed, such as invalidating the test results, or not taking them into consideration, etc.

[0101] In some embodiments of the present application, the first accident sequence is an accident sequence in which the contribution value of the pressurized water reactor core damage and the containment performance deterioration exceeds a preset threshold;

[0102] Before performing effectiveness detection on the pressurized water reactor containment pressure control system based on the first accident sequence with the highest core damage degree or the fastest accident progress corresponding to each accident type in step S800, the method further includes the following step S710:

[0103] Step S710: receiving a screening operation for a plurality of second accident sequences, where the second accident sequence is an accident sequence whose contribution value to pressurized water reactor core damage and containment performance deterioration is lower than a preset threshold.

[0104] Based on the first accident sequence corresponding to each accident type with the highest degree of core damage or the fastest accident process, the effectiveness of the pressurized water reactor containment pressure control system is tested, including the following steps S810:

[0105] Step S810: Based on the first accident sequence with the highest degree of core damage or the fastest accident process corresponding to each accident type and the multiple second accident sequences screened by the screening operation, the effectiveness of the pressurized water reactor containment pressure control system is detected.

[0106] In the process of screening accident sequences in the above embodiment, some accident sequences that also have contribution values ​​for causing damage to the core of the pressurized water reactor and deterioration of the performance of the containment vessel may be filtered out; therefore, in this embodiment, the accident sequence is supplemented, that is, a screening operation for multiple second accident sequences is received, and multiple second accident sequences can be screened out from the accident sequences screened out from the multiple accident sequences, the second accident sequence is an accident sequence whose contribution value for causing damage to the core of the pressurized water reactor and deterioration of the performance of the containment vessel is lower than a preset threshold, and the first accident sequence is an accident sequence whose contribution value for causing damage to the core of the pressurized water reactor and deterioration of the performance of the containment vessel is higher than a preset threshold (which can be set based on experience).

[0107] The method provided in this embodiment can supplement some accident sequences, increase the options for accident sequences detected by the pressurized water reactor containment pressure control system, and improve the flexibility of accident sequence selection.

[0108] It should be noted that the accident sequence can also be supplemented by other indicators, which can be set specifically by nuclear reactor operation experience. It should also be noted that the selected multiple second accident sequences can be merged in the same way as the first accident sequence to obtain the second accident sequence with the highest degree of core damage, so that it is a typical and enveloping accident sequence among the multiple second accident sequences.

[0109] In some embodiments of the present application, based on the first accident sequence corresponding to each accident type with the highest degree of core damage or the fastest accident process, before performing effectiveness detection on the pressurized water reactor containment pressure control system, the method further includes step S720:

[0110] Step S720: From the first accident sequences corresponding to each accident type, select a third accident sequence in which the accident progress speed is higher than the fifth threshold and the mass-energy release in the containment is greater than the sixth threshold.

[0111] In step S800, based on the first accident sequence corresponding to each accident type with the highest degree of core damage or the fastest accident process, the effectiveness of the pressurized water reactor containment pressure control system is tested, including the following step S820:

[0112] Step S820: Perform effectiveness detection on the pressurized water reactor containment pressure control system through the third accident sequence.

[0113] In this embodiment, the accident sequence in which the accident progress speed is higher than the fifth threshold and the mass-energy release in the containment is more than the sixth threshold refers to the accident sequence in which the mass-energy release in the containment is large and the accident progress is fast (this means that the core is exposed early and the core is degraded quickly). It should be noted that the mass-energy release in the containment of each accident sequence screened out here is quantified, and then the final screening is carried out based on the large mass-energy release in the containment (such as setting a fifth threshold for the release amount, and performing a threshold judgment on whether the release is large) and the fast accident progress (such as setting a sixth threshold).

[0114] After selecting the first accident sequence with the highest degree of core damage or the fastest accident progress among different accident types, the method provided in this embodiment continues to perform more refined screening on the first accident sequence with the highest degree of core damage or the fastest accident progress, thereby improving the precision of screening accident sequences;

[0115] It should be noted that it is also possible to only consider the third accident sequence in which the accident process speed is higher than the fifth threshold, or only consider the third accident sequence in which the mass-energy release in the containment is greater than the sixth threshold, which can also improve the precision of screening accident sequences.

[0116] For ease of understanding, the present application provides an embodiment, a method for detecting a pressurized water reactor containment pressure control system. Taking the Hualong One (or M310, CPR1000, etc.) pressurized water reactor nuclear power unit as an example, the method includes the following steps S910 to S960:

[0117] Step S910: Acquire multiple accident sequences.

[0118] Step S920: Determine multiple first accident sequences according to a probability analysis method.

[0119] Based on the model of first-level probabilistic safety analysis of internal events in nuclear power plants, event trees and fault trees are constructed, and the probability of core melting caused by each event sequence is calculated.

[0120] Based on the calculated sequence occurrence probability, the corresponding accident sequences are arranged in descending order of the probability of causing core melt.

[0121] The first accident sequence is selected from the above accident sequences according to the following principles:

[0122] Select accident sequences whose contribution to the core damage frequency exceeds a certain percentage;

[0123] Or, select the accident sequence with the top N occurrence probabilities as the first accident sequence (N is an integer);

[0124] Or, select the sequence whose core damage frequency is greater than a certain value;

[0125] Alternatively, select sequences that result in a radioactive release frequency greater than a certain value.

[0126] The above selection principles can be formulated based on regulatory requirements, unit characteristics, etc.

[0127] Step S930: classify the multiple first accident sequences and select the first accident sequence with the highest degree of core damage or the fastest accident progress in each category.

[0128] Group multiple first accident sequences with the same initiating event into one category;

[0129] Multiple first accident sequences with the same or similar accident processes are grouped into one category;

[0130] Sequences are merged according to the principle of "sequences with high unit status envelop sequences with low unit status, sequences with serious accident consequences envelop sequences with lighter accident consequences" (i.e. accident sequences with high core damage degree envelop accident sequences with low accident damage degree), or "accident sequences with fast accident progress envelop accident sequences with slow accident progress", and the accident sequences with the fastest accident progress or the highest core damage degree among similar accident sequences are selected. In this way, an enveloping, typical first accident sequence is selected for each accident type.

[0131] Taking a plant-wide power outage as an example, a sequence with high unit status envelops a sequence with low unit status, or a sequence with serious accident consequences envelops a sequence with lighter accident consequences: if a plant-wide power outage occurs under power conditions, because the core operates at full power under power conditions and the unit status (pressure, temperature, etc.) is high, the consequences caused are more serious than the consequences of a plant-wide power outage under shutdown conditions, so the former can envelop the latter.

[0132] The sequence with fast accident progress envelops the sequence with slow accident progress: for example, the injection system can replenish the core water to alleviate the core state. The initiating events of sequence 1 and sequence 2 are the same, but sequence 1 is the direct injection failure of the injection system, and sequence 2 is the injection system that is available in the direct injection stage but unavailable in the long-term stage. Therefore, from the perspective of accident development, the core damage process of sequence 1 is faster, and sequence 1 can envelop sequence 2.

[0133] Then, we need to eliminate accident sequences involving pressure vessel rupture; eliminate accident sequences involving reactivity that cannot be effectively controlled; eliminate accident sequences involving failure of shutdown signal to shut down the reactor; and eliminate accident sequences involving containment bypass.

[0134] Step S940, add the accident sequence that has been screened out but has made significant contributions to core damage and containment performance deterioration as the second accident sequence, and merge multiple second accident sequences again according to the merging principle of S930 to form the second accident sequence with the highest degree of core damage or the fastest accident progress.

[0135] Step S950: Determine a third accident sequence for testing system effectiveness:

[0136] Based on the first accident sequence and the second accident sequence screened out by the above method, an accident sequence with more mass-energy release in the containment and faster accident process is selected as the third accident sequence.

[0137] Step S960: Use the integrated severe accident analysis program to build a pressurized water reactor containment pressure control system of the nuclear power plant model, and perform calculation analysis on the third accident sequence. If the pressurized water reactor containment pressure can be effectively controlled, the effectiveness of the containment pressure control system can be proved. The integrated severe accident analysis program is common knowledge in the nuclear power field and will not be described in detail here.

[0138] This embodiment has the following advantages:

[0139] Screening out representative and enveloping accident sequences from a massive amount of accident sequences can improve the efficiency and quality of effectiveness testing of the pressurized water reactor containment pressure control system, and can prove that the overpressure relief of the containment pressure control system installed in the nuclear power plant has a sufficiently high credibility, which can ensure the safety of the public around the nuclear power plant under accident conditions.

[0140] Reference Figure 2 Some embodiments of the present application provide a detection device for a pressurized water reactor containment pressure control system, the device comprising an accident sequence acquisition unit 1100, an accident type classification unit 1200, an accident sequence selection unit 1300 and a control system detection unit 1400:

[0141] The accident sequence acquisition unit 1100 is used to acquire a plurality of first accident sequences, where the first accident sequence refers to an accident sequence having a probability of causing damage to the core of a pressurized water reactor;

[0142] The accident type classification unit 1200 is used to classify the multiple first accident sequences into accident types;

[0143] The accident sequence selection unit 1300 is used to merge the first accident sequences belonging to the same accident type according to the core damage degree or accident progress speed caused by the accident sequence, and obtain the first accident sequence with the highest core damage degree or the fastest accident progress corresponding to each accident type;

[0144] The control system detection unit 1400 is used to perform effectiveness detection on the pressure control system of the containment vessel of the pressurized water reactor based on the first accident sequence with the highest degree of core damage or the fastest accident progress corresponding to each accident type.

[0145] It should be noted that the detection device for the pressurized water reactor containment pressure control system provided in this embodiment and the detection method for the pressurized water reactor containment pressure control system described above are based on the same inventive concept, so the relevant contents of the detection method for the pressurized water reactor containment pressure control system described above are also applicable to the contents of the detection device for the pressurized water reactor containment pressure control system, and therefore, they will not be repeated here.

[0146] like Figure 3 The embodiment of the present application further provides an electronic device, the electronic device comprising:

[0147] At least one hydrogen fuel cell;

[0148] at least one memory;

[0149] at least one processor;

[0150] at least one program;

[0151] The program is stored in the memory, and the processor executes at least one program to implement the detection method of the pressurized water reactor containment pressure control system implemented in the present disclosure.

[0152] The electronic device may be any intelligent terminal including a mobile phone, a tablet computer, a personal digital assistant (PDA), a vehicle-mounted computer, etc.

[0153] The electronic device according to the embodiment of the present application is described in detail below.

[0154] The processor 1600 may be implemented by a general-purpose central processing unit (CPU), a microprocessor, an application-specific integrated circuit (ASIC), or one or more integrated circuits, and is used to execute relevant programs to implement the technical solutions provided in the embodiments of the present disclosure;

[0155] The memory 1700 can be implemented in the form of a read-only memory (ROM), a static storage device, a dynamic storage device, or a random access memory (RAM). The memory 1700 can store an operating system and other application programs. When the technical solution provided in the embodiments of this specification is implemented by software or firmware, the relevant program code is stored in the memory 1700, and the processor 1600 calls and executes a detection method for a pressurized water reactor containment pressure control system in the embodiment of the present disclosure.

[0156] Input / output interface 1800, used to implement information input and output;

[0157] The communication interface 1900 is used to realize the communication interaction between the device and other devices. The communication can be realized through a wired manner (such as USB, network cable, etc.) or a wireless manner (such as mobile network, WIFI, Bluetooth, etc.);

[0158] Bus 2000 , which transmits information between various components of the device (e.g., processor 1600 , memory 1700 , input / output interface 1800 , and communication interface 1900 );

[0159] The processor 1600 , the memory 1700 , the input / output interface 1800 , and the communication interface 1900 are connected to each other in communication within the device via the bus 2000 .

[0160] The embodiment of the present disclosure also provides a storage medium, which is a computer-readable storage medium. The computer-readable storage medium stores computer-executable instructions, and the computer-executable instructions are used to enable a computer to execute the above-mentioned detection method of the pressurized water reactor containment pressure control system.

[0161] The memory, as a non-transient computer-readable storage medium, can be used to store non-transient software programs and non-transient computer executable programs. In addition, the memory may include a high-speed random access memory, and may also include a non-transient memory, such as at least one disk storage device, a flash memory device, or other non-transient solid-state storage device. In some embodiments, the memory may optionally include a memory remotely disposed relative to the processor, and these remote memories may be connected to the processor via a network. Examples of the above-mentioned network include, but are not limited to, the Internet, an intranet, a local area network, a mobile communication network, and combinations thereof.

[0162] The embodiments described in the embodiments of the present disclosure are intended to more clearly illustrate the technical solutions of the embodiments of the present disclosure and do not constitute a limitation on the technical solutions provided by the embodiments of the present disclosure. Those skilled in the art will appreciate that with the evolution of technology and the emergence of new application scenarios, the technical solutions provided by the embodiments of the present disclosure are also applicable to similar technical problems.

[0163] Those skilled in the art will appreciate that the technical solutions shown in the figures do not limit the embodiments of the present disclosure and may include more or fewer steps than shown in the figures, or a combination of certain steps, or different steps.

[0164] The device embodiments described above are merely illustrative, and the units described as separate components may or may not be physically separated, that is, they may be located in one place or distributed on multiple network units. Some or all of the modules may be selected according to actual needs to achieve the purpose of the solution of this embodiment.

[0165] Those skilled in the art will appreciate that all or some of the steps in the methods disclosed above, and the functional modules / units in the systems and devices may be implemented as software, firmware, hardware, or a suitable combination thereof.

[0166] The terms "first", "second", "third", "fourth", etc. (if any) in the specification of the present application and the above-mentioned drawings are used to distinguish similar objects, and are not necessarily used to describe a specific order or sequence. It should be understood that the data used in this way can be interchangeable where appropriate, so that the embodiments of the present application described herein can be implemented in an order other than those illustrated or described herein. In addition, the terms "including" and "having" and any of their variations are intended to cover non-exclusive inclusions, for example, a process, method, system, product or device comprising a series of steps or units is not necessarily limited to those steps or units clearly listed, but may include other steps or units that are not clearly listed or inherent to these processes, methods, products or devices.

[0167] It should be understood that in the present application, "at least one (item)" means one or more, and "plurality" means two or more. "And / or" is used to describe the association relationship of associated objects, indicating that three relationships may exist. For example, "A and / or B" can mean: only A exists, only B exists, and A and B exist at the same time, where A and B can be singular or plural. The character " / " generally indicates that the objects associated before and after are in an "or" relationship. "At least one of the following" or similar expressions refers to any combination of these items, including any combination of single or plural items. For example, at least one of a, b or c can mean: a, b, c, "a and b", "a and c", "b and c", or "a and b and c", where a, b, c can be single or multiple.

[0168] In the several embodiments provided in the present application, it should be understood that the disclosed devices and methods can be implemented in other ways. For example, the device embodiments described above are only schematic. For example, the division of units is only a logical function division. There may be other division methods in actual implementation, such as multiple units or components can be combined or integrated into another system, or some features can be ignored or not executed. Another point is that the mutual coupling or direct coupling or communication connection shown or discussed can be through some interfaces, indirect coupling or communication connection of devices or units, which can be electrical, mechanical or other forms.

[0169] The units described as separate components may or may not be physically separated, and the components shown as units may or may not be physical units, that is, they may be located in one place or distributed on multiple network units. Some or all of the units may be selected according to actual needs to achieve the purpose of the solution of this embodiment.

[0170] In addition, each functional unit in each embodiment of the present application may be integrated into one processing unit, or each unit may exist physically separately, or two or more units may be integrated into one unit. The above-mentioned integrated unit may be implemented in the form of hardware or in the form of software functional units.

[0171] If the integrated unit is implemented in the form of a software functional unit and sold or used as an independent product, it can be stored in a computer-readable storage medium. Based on this understanding, the technical solution of the present application is essentially or the part that contributes to the prior art or all or part of the technical solution can be embodied in the form of a software product, and the computer software product is stored in a storage medium, including multiple instructions to enable an electronic device (which can be a personal computer, server, or network device, etc.) to execute all or part of the steps of each embodiment method of the present application. The aforementioned storage medium includes: U disk, mobile hard disk, read-only memory (Read-Only Memory, ROM), random access memory (Random Access Memory, RAM), disk or optical disk and other media that can store programs.

[0172] The above is a specific description of the preferred implementation of the embodiments of the present application, but the embodiments of the present application are not limited to the above-mentioned implementation methods. Technical personnel familiar with the field can also make various equivalent modifications or substitutions without violating the spirit of the embodiments of the present application. These equivalent modifications or substitutions are all included in the scope defined by the claims of the embodiments of the present application.

Claims

1. A method for detecting a pressure control system of a pressurized water reactor containment vessel, characterized in that: The method comprises: Acquire a plurality of first accident sequences, where the first accident sequence refers to an accident sequence having a probability of causing damage to a pressurized water reactor core; Classifying the multiple first accident sequences into accident types; The first accident sequences belonging to the same accident type are merged according to the core damage degree or accident progress speed caused by the accident sequence, and the first accident sequence with the highest core damage degree or the fastest accident progress corresponding to each accident type is obtained; Based on the first accident sequence corresponding to each accident type, which has the highest degree of core damage or the fastest accident process, the effectiveness of the pressurized water reactor containment pressure control system is detected.

2. The detection method of the pressurized water reactor containment pressure control system according to claim 1, characterized in that: The obtaining of a plurality of first accident sequences comprises: Obtain multiple accident sequences; Determining the index value of the evaluation index of the impact of each of the accident sequences on the pressurized water reactor containment; The plurality of first accident sequences are obtained by screening the plurality of accident sequences based on an index value of an evaluation index of an impact of each of the accident sequences on a pressurized water reactor containment.

3. The detection method of the pressurized water reactor containment pressure control system according to claim 2, characterized in that: The step of selecting the plurality of first accident sequences from the plurality of accident sequences based on the index value of the evaluation index of the impact of each of the accident sequences on the pressurized water reactor containment shell comprises at least one of the following: If the index value includes a probability value of a pressurized water reactor core melt caused by the accident sequence, then selecting the accident sequence whose probability value is greater than a first threshold from the multiple accident sequences as a first accident sequence; If the indicator value includes a first frequency value of pressurized water reactor core damage caused by the accident sequence, selecting the accident sequence whose first frequency value is greater than a second threshold value from the multiple accident sequences as a first accident sequence; If the indicator value includes a second frequency value of radioactive release caused by the accident sequence, selecting the accident sequence whose second frequency value is greater than a third threshold value from the multiple accident sequences as the first accident sequence; If the index value includes the contribution of the core damage frequency caused by the accident sequence, the accident sequence whose contribution is greater than a fourth threshold is selected from the multiple accident sequences as the first accident sequence.

4. The detection method of the pressurized water reactor containment pressure control system according to claim 1, characterized in that: Before classifying the multiple first accident sequences into accident types, the method further includes: Eliminating some of the first accident sequences that meet the elimination conditions among the multiple first accident sequences; The classifying the multiple first accident sequences into accident types includes: Classifying the multiple first accident sequences after excluding some of the first accident sequences by accident type; The elimination conditions include: The accident sequence leading to the rupture of the pressure vessel; Accident sequences that result in reactivity that cannot be effectively controlled; Accident sequence resulting in failure of shutdown signal and inability to shutdown the reactor; Accident sequences resulting in a containment bypass type.

5. The detection method of the pressurized water reactor containment pressure control system according to claim 1, characterized in that: The first accident sequence is an accident sequence in which the contribution value of the damage to the core of the pressurized water reactor and the deterioration of the performance of the containment exceeds a preset threshold; Before performing effectiveness detection on the pressurized water reactor containment pressure control system based on the first accident sequence corresponding to each accident type with the highest degree of core damage or the fastest accident progress, the method further includes: receiving a screening operation for a plurality of second accident sequences, where the second accident sequence is an accident sequence whose contribution value to pressurized water reactor core damage and containment performance deterioration is lower than a preset threshold; The effectiveness detection of the pressurized water reactor containment pressure control system based on the first accident sequence corresponding to each accident type with the highest degree of core damage or the fastest accident process includes: Based on the first accident sequence corresponding to the highest degree of core damage or the fastest accident process for each accident type and the multiple second accident sequences screened by the screening operation, the effectiveness of the pressurized water reactor containment pressure control system is detected.

6. The detection method of the pressurized water reactor containment pressure control system according to claim 1, characterized in that: Before performing effectiveness detection on the pressurized water reactor containment pressure control system based on the first accident sequence corresponding to each accident type with the highest degree of core damage or the fastest accident progress, the method further includes: From the first accident sequences corresponding to each accident type, the first accident sequence in which the accident progress speed is higher than the fifth threshold and the mass energy release in the containment is higher than the sixth threshold is selected as the third accident sequence; The effectiveness detection of the pressurized water reactor containment pressure control system based on the first accident sequence corresponding to each accident type with the highest degree of core damage or the fastest accident process includes: The effectiveness of the pressurized water reactor containment pressure control system is detected through the third accident sequence.

7. The detection method of the pressurized water reactor containment pressure control system according to claim 1, characterized in that: The classifying the multiple first accident sequences into accident types includes at least one of the following: Classifying the first accident sequences having the same initiating event into the same accident type; Classifying the first accident sequences having a unique initiating event and the same accident process among the multiple first accident sequences into the same accident type; The first accident sequences having a unique initiating event and having a similarity higher than a seventh threshold among the multiple first accident sequences are classified into the same accident type.

8. A detection device for a pressurized water reactor containment pressure control system, characterized in that: The device comprises: An accident sequence acquisition unit, configured to acquire a plurality of first accident sequences, wherein the first accident sequence refers to an accident sequence having a probability of causing damage to the core of a pressurized water reactor; An accident type classification unit, configured to classify the multiple first accident sequences into accident types; An accident sequence selection unit is used to merge the first accident sequences belonging to the same accident type according to the core damage degree or accident progress speed caused by the accident sequence, and obtain the first accident sequence with the highest core damage degree or the fastest accident progress corresponding to each accident type; The control system detection unit is used to detect the effectiveness of the pressure control system of the containment vessel of the pressurized water reactor based on the first accident sequence corresponding to each accident type with the highest degree of core damage or the fastest accident process.

9. An electronic device, characterized in that: It includes at least one control processor and a memory for communicating with the at least one control processor; the memory stores instructions that can be executed by the at least one control processor, and the instructions are executed by the at least one control processor so that the at least one control processor can execute the detection method of a pressurized water reactor containment pressure control system as described in any one of claims 1 to 7.

10. A computer-readable storage medium, characterized in that: The computer-readable storage medium stores computer-executable instructions, and the computer-executable instructions are used to enable a computer to execute the detection method for a pressurized water reactor containment pressure control system according to any one of claims 1 to 7.

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