CN115730764A

CN115730764A - Nuclear power plant safety design analysis method, apparatus, device, medium, and program product

Info

Publication number: CN115730764A
Application number: CN202211423611.8A
Authority: CN
Inventors: 欧平文; 刘萍萍; 安云娜; 陈鹏; 贺东钰; 江娉婷
Original assignee: China General Nuclear Power Corp; China Nuclear Power Technology Research Institute Co Ltd; CGN Power Co Ltd
Current assignee: China General Nuclear Power Corp; China Nuclear Power Technology Research Institute Co Ltd; CGN Power Co Ltd
Priority date: 2022-11-15
Filing date: 2022-11-15
Publication date: 2023-03-03

Abstract

The application relates to a nuclear power plant safety design analysis method, a device, equipment, a medium and a program product. The method comprises the following steps: the method comprises the steps of obtaining radioactive source information of a nuclear power plant and obtaining radioactive leakage path information of the nuclear power plant; determining a plurality of different leakage accident condition information according to the radioactive source information and the radioactive leakage path information; determining the occurrence probability corresponding to each leakage accident condition information; and acquiring a target judgment result aiming at the nuclear power plant based on the occurrence probability corresponding to each leakage accident condition information and the sum of the occurrence probabilities corresponding to each leakage accident condition information, wherein the target judgment result is used for indicating whether the nuclear power plant meets the condition of actually eliminating early radioactive release or a large amount of radioactive release. The method and the device realize the quantitative analysis on safety of the design of the nuclear power plant, thereby improving the accuracy of the safety design analysis result of the nuclear power plant.

Description

Nuclear power plant safety design analysis method, apparatus, device, medium, and program product

Technical Field

The present application relates to the field of nuclear power plant design technologies, and in particular, to a method, an apparatus, a device, a medium, and a program product for analyzing a safety design of a nuclear power plant.

Background

The concept of "practically eliminating the release of a large amount of radioactivity" was first proposed by the nuclear Safety review agency in France and Germany and by the Nuclear Safety Commission on GPR/RSK Proposals for a Common Safety Approach for Future Pressurized Water Reactors, with the aim of setting Safety design goals for the next generation of Pressurized Water reactor nuclear power plants. Since early release of containment accounts for a large share of radioactive release, the release of HAF102-2016 design safety regulations for nuclear power plants, approved by the national Nuclear safety administration at 26 months 10 years 2016, requires: accident conditions which can cause the early release of a large amount of radioactivity in the containment vessel must be 'actually eliminated', and if the accident conditions are substantially impossible or extremely impossible to occur with high confidence level, the condition is considered to be 'actually eliminated'; it must be ensured that the nuclear power plant can enter a controlled state and maintain containment functionality so that the possibility of the occurrence of a controlled state of the nuclear power plant resulting in early radioactive emissions or significant radioactive emissions can be virtually eliminated. At present, the problem that the accuracy of an analysis result is low and the like exists because qualitative analysis is mostly carried out aiming at safety of design of a nuclear power plant.

Disclosure of Invention

In view of the above, there is a need to provide a method, an apparatus, a device, a medium, and a program product for analyzing safety design of a nuclear power plant, which can quantitatively analyze whether the design of the nuclear power plant is safe, thereby improving accuracy of analysis results.

In a first aspect, the application provides a nuclear power plant safety design analysis method. The method comprises the following steps: acquiring radioactive source information of a nuclear power plant, and acquiring radioactive leakage path information of the nuclear power plant; determining a plurality of different leakage accident condition information according to the radioactive source information and the radioactive leakage path information; determining the occurrence probability corresponding to the working condition information of each leakage accident; and acquiring a target judgment result aiming at the nuclear power plant based on the occurrence probability corresponding to each leakage accident condition information and the sum of the occurrence probabilities corresponding to each leakage accident condition information, wherein the target judgment result is used for indicating whether the nuclear power plant meets the condition of actually eliminating early radioactive release or a large amount of radioactive release.

In one embodiment, obtaining a target judgment result for the nuclear power plant based on the occurrence probability corresponding to each leakage accident condition information and the sum of the occurrence probabilities corresponding to each leakage accident condition information includes: acquiring a preset probability target value and a safety factor; determining a probability reference value according to the probability target value and the safety factor; and determining a target judgment result according to whether the occurrence probability corresponding to each leakage accident condition information is smaller than the probability reference value and whether the sum value is smaller than the probability target value.

In one embodiment, determining the target judgment result according to whether the occurrence probability corresponding to each leakage accident condition information is smaller than a probability reference value and whether the sum value is smaller than a probability target value includes: if the occurrence probability corresponding to each leakage accident condition information is smaller than the probability reference value and the sum value is smaller than the probability target value, taking a first result as a target judgment result, wherein the first result indicates that the nuclear power plant meets the condition of actually eliminating early radioactivity release or a large amount of radioactivity release; and if the leakage accident condition information with the occurrence probability larger than or equal to the probability reference value exists in the leakage accident condition information, or the sum value is larger than or equal to the probability target value, taking a second result as a target judgment result, wherein the second result indicates that the nuclear power plant does not meet the condition of actually eliminating early radioactive release or a large amount of radioactive release.

In one embodiment, the method for analyzing the safety design of the nuclear power plant further comprises: for each leakage accident condition information, judging and processing the leakage accident condition information to obtain the occurrence probability corresponding to the leakage accident condition information; wherein the judgment process includes at least one of a first judgment process and a second judgment process, wherein the first judgment process includes: inputting the leakage accident condition information into a preset nuclear power plant accident analysis program, and judging and processing the leakage accident condition information by the nuclear power plant accident analysis program based on the arrangement geometric information of the nuclear power plant, system equipment parameters and accident hypothesis; the second determination process includes: inputting the information of the leakage accident condition into a preset risk analysis program, constructing a PSA model based on the information of the leakage accident condition by the risk analysis program, and judging and processing the information of the leakage accident condition aiming at the PSA model.

In one embodiment, determining a plurality of different leakage accident condition information according to the radioactive source information and the radioactive leakage path information comprises: determining the fault type of radioactive leakage, wherein the fault type comprises a stress failure type and a structural failure type; according to the radioactive source information and the radioactive leakage path information, a plurality of different leakage accident working conditions are constructed according to the fault types, and a plurality of different leakage accident working condition information are obtained according to the constructed different leakage accident working conditions.

In one embodiment, obtaining radioactive source information for a nuclear power plant includes: determining a radioactive component in the nuclear power plant according to the type of the nuclear power plant, wherein the radioactive component can generate radioactive release; and taking the position information of the radioactive component in the nuclear power plant as the radioactive source information.

In one embodiment, acquiring the radioactive leakage path information of the nuclear power plant comprises: determining a radioactive barrier component disposed between a radioactive component in a nuclear power plant and an external environment; and determining a possible radioactive leakage path in the radioactive barrier component, and using the position information of the radioactive leakage path in the radioactive barrier component as the radioactive leakage path information.

In a second aspect, the application further provides a nuclear power plant safety design analysis device. The device comprises: the system comprises a first acquisition module, a second acquisition module and a third acquisition module, wherein the first acquisition module is used for acquiring radioactive source information of a nuclear power plant and acquiring radioactive leakage path information of the nuclear power plant; the first determining module is used for determining a plurality of different leakage accident condition information according to the radioactive source information and the radioactive leakage path information; the second determining module is used for determining the occurrence probability corresponding to the working condition information of each leakage accident; and the second acquisition module is used for acquiring a target judgment result aiming at the nuclear power plant based on the occurrence probability corresponding to each leakage accident condition information and the sum of the occurrence probabilities corresponding to each leakage accident condition information, wherein the target judgment result is used for indicating whether the nuclear power plant meets the condition of actually eliminating early radioactive release or a large amount of radioactive release.

In one embodiment, the second obtaining module is further configured to obtain a preset probability target value and a safety factor; determining a probability reference value according to the probability target value and the safety coefficient; and determining a target judgment result according to whether the occurrence probability corresponding to each leakage accident condition information is smaller than the probability reference value and whether the sum value is smaller than the probability target value.

In one embodiment, the second obtaining module is further configured to, if the occurrence probability corresponding to each leakage accident condition information is smaller than a probability reference value and the sum value is smaller than a probability target value, take a first result as a target judgment result, where the first result indicates that the nuclear power plant meets a condition of actually eliminating early radioactivity release or a large amount of radioactivity release; and if the leakage accident condition information with the occurrence probability larger than or equal to the probability reference value exists in the leakage accident condition information, or the sum value is larger than or equal to the probability target value, taking a second result as a target judgment result, wherein the second result indicates that the nuclear power plant does not meet the condition of actually eliminating early radioactive release or a large amount of radioactive release.

In one embodiment, the second determining module is further configured to perform judgment processing on each leakage accident condition information according to the leakage accident condition information to obtain an occurrence probability corresponding to the leakage accident condition information; wherein the judgment process includes at least one of a first judgment process and a second judgment process, wherein the first judgment process includes: inputting the leakage accident condition information into a preset nuclear power plant accident analysis program, and judging and processing the leakage accident condition information by the nuclear power plant accident analysis program based on the arrangement geometric information of the nuclear power plant, system equipment parameters and accident hypothesis; the second determination process includes: inputting the information of the leakage accident condition into a preset risk analysis program, constructing a PSA model based on the information of the leakage accident condition by the risk analysis program, and judging and processing the information of the leakage accident condition aiming at the PSA model.

In one embodiment, the first determining module is further configured to determine a failure type of the radioactive leakage, where the failure type includes a stress failure type and a structural failure type; according to the radioactive source information and the radioactive leakage path information, a plurality of different leakage accident working conditions are constructed according to the fault types, and a plurality of different leakage accident working condition information are obtained according to the constructed plurality of different leakage accident working conditions.

In one embodiment, the first obtaining module is further configured to determine a radioactive component in the nuclear power plant according to a type of the nuclear power plant, where the radioactive component may generate a radioactive release; and taking the position information of the radioactive component in the nuclear power plant as the radioactive source information.

In one embodiment, the first obtaining module is further configured to determine a radioactive barrier component disposed between a radioactive component and an external environment in the nuclear power plant; and determining a possible radioactive leakage path in the radioactive barrier component, and using the position information of the radioactive leakage path in the radioactive barrier component as the radioactive leakage path information.

In a third aspect, the present application further provides a computer device comprising a memory and a processor, the memory storing a computer program, the processor implementing the steps of the method according to any one of the first aspect when executing the computer program.

In a fourth aspect, the present application also provides a computer-readable storage medium having stored thereon a computer program which, when executed by a processor, performs the steps of the method of any of the first aspects described above.

In a fifth aspect, the present application also provides a computer program product comprising a computer program that, when executed by a processor, performs the steps of the method of any of the first aspects described above.

According to the nuclear power plant safety design analysis method, the device, the equipment, the medium and the program product, the radioactivity source information of the nuclear power plant is obtained, the radioactivity leakage path information of the nuclear power plant is obtained, a plurality of different leakage accident condition information is determined according to the radioactivity source information and the radioactivity leakage path information, the occurrence probability corresponding to each leakage accident condition information is determined, and the target judgment result for the nuclear power plant is obtained based on the occurrence probability corresponding to each leakage accident condition information and the sum value of the occurrence probabilities corresponding to each leakage accident condition information, wherein the target judgment result is used for indicating whether the nuclear power plant meets the condition of actually eliminating early radioactivity release or massive radioactivity release. Whether safe target judgment result of the design of nuclear power plant is obtained through the occurrence probability corresponding to each leakage accident condition information and the sum of the occurrence probability corresponding to each leakage accident condition information, whether safe quantitative analysis of the design of the nuclear power plant is achieved, and therefore the accuracy of the safety design analysis result of the nuclear power plant is improved.

Drawings

FIG. 1 is a schematic flow chart of a nuclear power plant safety design analysis method in one embodiment;

FIG. 2 is a schematic flow chart diagram of another method for analyzing a nuclear power plant safety design in one embodiment;

FIG. 3 is a block diagram of a nuclear power plant safety design analysis device according to an embodiment;

FIG. 4 is a diagram of the internal structure of a computer device in one embodiment.

Detailed Description

In order to make the objects, technical solutions and advantages of the present application more clearly understood, the present application is further described in detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative of the present application and are not intended to limit the present application.

In an embodiment, as shown in fig. 1, a flowchart of a method for analyzing a safety design of a nuclear power plant is provided, and this embodiment is illustrated by applying the method to a terminal, it is to be understood that the method may also be applied to a server, and may also be applied to a system including the terminal and the server, and implemented by interaction between the terminal and the server, where the terminal may be, but is not limited to, various personal computers, notebook computers, smart phones, tablet computers, and the like. The server may be implemented as a stand-alone server or as a server cluster consisting of a plurality of servers. In the embodiment of the application, the method comprises the following steps:

step 101, acquiring radioactive source information of a nuclear power plant, and acquiring radioactive leakage path information of the nuclear power plant.

The nuclear power plants are of various types, including a pressurized water reactor nuclear power plant, a boiling water reactor nuclear power plant, a high temperature gas cooled reactor nuclear power plant, a heavy water reactor nuclear power plant, a pressure tube type graphite moderating boiling water reactor nuclear power plant and a sodium-cooled fast reactor nuclear power plant. Nuclear fuel (including spent fuel) is a source of early radioactive emissions or large radioactive emissions in a nuclear power plant, and the source of the radioactive emissions can be identified by confirming the location of the nuclear fuel in the nuclear power plant, so that the radioactive source information can be the location information of the nuclear fuel in the nuclear power plant. Different nuclear power plants, such as pressurized water reactor nuclear power plants, have different radioactive sources, such as a reactor pressure vessel and a spent fuel pool, due to different locations for storing nuclear fuel. The radioactive leakage path is a passage between the radioactive source and the external environment, which is established by the radioactive source breaking through a radioactive barrier isolated from the external environment, and at least one radioactive leakage path, such as a reactor pressure vessel in a pressurized water reactor nuclear power plant, can be determined by the radioactive source, wherein the radioactive leakage path comprises a containment body, a containment bottom and a bypass containment, and the bypass containment is a joint on the containment with other components. The radioactive barriers may be different for different radioactive sources and thus the radioactive leakage paths may be different. The radioactive leakage path information is location information of the radioactive leakage path, such as may be location information of at least one point on the containment body, location information of at least one point in the bottom of the containment and location information of at least one point on the bypass containment.

Optionally, in a stage of designing the nuclear power plant, the terminal obtains radioactive source information and radioactive barrier information according to the radioactive source identifier and the radioactive barrier identifier in the nuclear power plant design drawing, and then a trained training model set in the terminal determines at least one possible radioactive leakage path according to the radioactive source information and the radioactive barrier information, so as to obtain at least one radioactive leakage path information and at least one radioactive leakage path identifier, where the radioactive leakage path identifier is used to uniquely identify the radioactive leakage path, such as 0011 — containment body a region, and the radioactive leakage path identifier corresponds to the radioactive leakage path information one to one, such as 0011- (0.3, 2, 4). It should be noted that the radioactive source identifier is different for different radioactive sources, and the radioactive barrier identifier is different for different radioactive barriers.

Compared with the traditional mode of judging the radioactive leakage path according to manual experience, the method of determining the radioactive leakage path through the training model enables the obtained radioactive leakage path information to be closer to the actual situation, namely the accuracy of the obtained radioactive leakage path information is higher.

And 102, determining a plurality of different leakage accident condition information according to the radioactive source information and the radioactive leakage path information.

The leakage accident condition information represents the cause of radioactive leakage, such as reactor core melt-Concrete Interaction (MCCI), direct Containment Heating (DCH), hydrogen explosion, steam explosion, late overpressure failure of the Containment, rupture of a primary circuit main pressure-bearing component, a large number of reactivity introduction accidents, containment bypass accidents, serious accidents of Containment opening, and fuel burndown of a spent fuel pool. Different radioactive source information and radioactive leakage path information may generate different leakage accident condition information and may also generate the same leakage accident condition information. In particular, after a severe leak accident condition occurs, if timely mitigation is not performed, the pressure vessel may fail. If the Pressure of the core is High at the time of Pressure vessel failure, high Pressure melt blowing (HPME) occurs, which may lead to DCH. The entrained melt enters the containment vessel, so that the pressure in the containment vessel is increased or the hydrogen in the containment vessel is ignited, and the hydrogen is rapidly combusted or exploded. And meanwhile, high-temperature molten material flying into the containment vessel can damage related systems, equipment and monitoring systems in the containment vessel, so that early threat to the integrity of the containment vessel can be caused, and early radioactive release or large radioactive release can be caused.

Optionally, the terminal may calculate to obtain the distance between the radioactive source and the radioactive leakage path according to the radioactive source information and the radioactive leakage path information, and then the trained model in the terminal may analyze to obtain at least one leakage accident condition information according to the distance between the radioactive source and the radioactive leakage path, the radioactive source and the radioactive leakage path. If the distance between the radioactive source and the radioactive leakage path is 2 meters, the radioactive source is a reactor core, the radioactive leakage path is a containment body B area, and the leakage accident condition information obtained by the terminal is DCH.

Compared with the traditional mode of determining the leakage accident condition information according to manual experience, the mode of determining the leakage accident condition information through the training model enables the obtained leakage accident condition information to be closer to the actual condition, and the accuracy of the obtained leakage accident condition information is higher.

And 103, determining the occurrence probability corresponding to each leakage accident condition information.

In the design of the nuclear power plant, a safety system and/or a release system are generally designed, and the occurrence probability corresponding to the leakage accident condition information refers to the probability of the leakage accident condition occurring under the safety system and/or the release system of the nuclear power plant. Specifically, the safety design of the nuclear power plant follows the concept of deep defense, and the design of a diversified redundant safety system and/or mitigation system aims to ensure the safety of the nuclear power plant. After the leakage accident condition occurs, the safety system and/or the relieving system of the nuclear power plant can relieve the leakage accident condition to prevent the reactor core from melting. If the mitigation fails, resulting in core melting, the high pressure train needs to be converted to a low pressure train to avoid high pressure meltblowing. After an initiating event occurs, two redundant arrays of reactor protection systems may ensure a reactor trip. The design benchmark accident relieving system mainly comprises a safe injection system, an emergency water supplementing system and a steam atmospheric emission system, and the systems relieve the leakage accident condition and maintain the safe state of the reactor. If the design benchmark accident is superimposed on the failure of the safety system or multiple initial events, the design benchmark accident will be changed into a design expansion working condition A accident. The design expansion working condition A accident relieving system mainly comprises a manual charging and discharging action, an emergency boronizing system, a secondary side passive waste heat discharging system and the like. If the reactor fails to stop, the reactor becomes an expected transient of failure to stop, and the same is true of the design expansion working condition A accident. The safety design of the design benchmark accident and the design extension condition A accident prevents the reactor core from melting. If these safety and/or mitigation systems fail, the core melts and enters a severe leak accident condition. Under the working condition of DCH, the system for relieving the pressure-relief accident mainly comprises a pressure relief valve special for serious accidents, and the pressure relief valve special for serious accidents can realize the conversion from a high-pressure sequence to a low-pressure sequence, so that the DCH is avoided, and the integrity of the containment is ensured.

Optionally, the terminal identifies and combs the safety system and/or the mitigation system for preventing each leakage accident condition from a preset database of a plurality of safety systems and/or mitigation systems designed for various leakage accident conditions of the nuclear power plant in advance according to the information of each leakage accident condition, and determines the safety system and/or the mitigation system corresponding to each leakage accident condition. And then, calculating the occurrence probability corresponding to the information of each leakage accident condition under the corresponding Safety system and/or relief system by using a determinism Analysis program and a probability theory Analysis program, wherein the probability theory Analysis program comprises a PSA (Probabilistic Safety Analysis) model. The occurrence probability corresponding to the leakage accident condition information calculated by the determinism analysis program is either 1 or 0; the probability of occurrence corresponding to the leakage accident condition information calculated by the probability theory analysis program is between 0 and 1. It should be noted that, for different leakage accident conditions, one of a deterministic theory analysis program and a probabilistic theory analysis program is adopted, for example, a deterministic theory analysis program is adopted for designing a benchmark accident and designing an extended condition a accident, and a probabilistic theory analysis program is adopted for a pressure relief valve special for a serious accident.

And 104, acquiring a target judgment result aiming at the nuclear power plant based on the occurrence probability corresponding to each leakage accident condition information and the sum of the occurrence probabilities corresponding to each leakage accident condition information, wherein the target judgment result is used for indicating whether the nuclear power plant meets the condition of actually eliminating early radioactive release or a large amount of radioactive release.

Optionally, the terminal compares the occurrence probability corresponding to each leakage accident condition information with one tenth of the probability safety target, and if the occurrence probability corresponding to each leakage accident condition information is less than one tenth of the probability safety target, it indicates that the early radioactivity release or a large amount of radioactivity release generated by the leakage accident condition corresponding to the leakage accident condition information can be eliminated or alleviated by the safety system and/or the alleviation system, so that it can be determined that the safety system and/or the alleviation system designed by the nuclear power plant for the leakage accident condition is qualified; if the occurrence probability corresponding to the leakage accident condition information is more than or equal to one tenth of the probability safety target, it is indicated that the early radioactivity release or the large amount of radioactivity release generated by the leakage accident condition corresponding to the leakage accident condition information cannot be eliminated or relieved by the safety system and/or the relief system, so that it can be determined that the safety system and/or the relief system designed by the nuclear power plant for the leakage accident condition is unqualified, and the safety system and/or the relief system of the nuclear power plant needs to be redesigned, wherein the one tenth of the probability safety target can be 10 ^-7 Pile-year.

Optionally, the terminal compares the sum of the occurrence probabilities corresponding to the leakage accident condition information with the probability safety target, and if the sum of the occurrence probabilities corresponding to the leakage accident condition information is smaller than the probability safety target, it is indicated that the safety design of the nuclear power plant is qualified, and early radioactivity release or a large amount of radioactivity release generated by a plurality of leakage accident conditions can be practically eliminated; if the sum of the occurrence probabilities corresponding to the leakage accident condition information is greater than or equal to the probability safety target, it is indicated that the safety design of the nuclear power plant is unqualified, early radioactivity release or a large amount of radioactivity release generated by a plurality of leakage accident conditions cannot be practically eliminated, and the safety design of the nuclear power plant needs to be carried out again, wherein the probability safety target can be 10 ^-6 Pile-year.

Optionally, there are four target determination results for the nuclear power plant, the first is that the occurrence probability corresponding to each piece of leaked accident condition information is less than one tenth of the probability safety target, and the sum of the occurrence probabilities corresponding to each piece of leaked accident condition information is less than the probability safety target; the second is that the occurrence probability corresponding to each leakage accident condition information is less than one tenth of the probability safety target, and the sum of the occurrence probabilities corresponding to each leakage accident condition information is greater than or equal to the probability safety target; thirdly, the occurrence probability corresponding to at least one leakage accident condition information is more than or equal to one tenth of the probability safety target, and the sum of the occurrence probabilities corresponding to all the leakage accident condition information is less than the probability safety target; and fourthly, the occurrence probability corresponding to at least one leakage accident condition information is more than or equal to one tenth of the probability safety target, and the sum of the occurrence probabilities corresponding to all the leakage accident condition information is more than or equal to the probability safety target. The first target judgment result indicates that the safety design of the nuclear power plant meets the actual elimination of early radioactive release or large radioactive release, and the other target judgment results indicate that the safety design of the nuclear power plant does not meet the actual elimination of early radioactive release or large radioactive release.

For example, the occurrence probability of a design reference accident is 0, the occurrence probability of a design expansion working condition A accident is 0, the pressure relief capacity of the pressure relief valve special for a serious accident is enough to reduce the pressure of a primary circuit to be lower than 2.0MPa when a pressure container fails, and the occurrence probability of HPME and DCH that the pressure relief valve cannot relieve the pressure is 10-9/heap year, so that the safety design aiming at the design reference accident, the design expansion working condition A accident and the pressure relief accident is qualified, and early radioactive release or a large amount of radioactive release can be eliminated actually.

By judging whether the occurrence probability corresponding to each leakage accident condition information is less than one tenth of the probability safety target and judging whether the sum of the occurrence probability corresponding to each leakage accident condition information is less than the probability safety target under the safety system and/or the relieving system, the quantitative analysis of the safety design of the nuclear power plant by the subentry probability and the total probability is realized, the design defects of the nuclear power plant can be accurately identified, and the feasibility is high in practical application.

In summary, by acquiring the radioactive source information of the nuclear power plant and the radioactive leakage path information of the nuclear power plant, determining a plurality of different leakage accident condition information according to the radioactive source information and the radioactive leakage path information, then determining the occurrence probability corresponding to each leakage accident condition information, and then acquiring a target judgment result for the nuclear power plant based on the occurrence probability corresponding to each leakage accident condition information and the sum of the occurrence probabilities corresponding to each leakage accident condition information, wherein the target judgment result is used for indicating whether the nuclear power plant meets the condition of actually eliminating early radioactive release or a large amount of radioactive release. Whether safe target judgment result of the design of nuclear power plant is obtained through the occurrence probability corresponding to each leakage accident condition information and the sum of the occurrence probability corresponding to each leakage accident condition information, whether safe quantitative analysis of the design of the nuclear power plant is achieved, and therefore the accuracy of the safety design analysis result of the nuclear power plant is improved.

In one embodiment, obtaining a target judgment result for the nuclear power plant based on the occurrence probability corresponding to each piece of leakage accident condition information and the sum of the occurrence probabilities corresponding to each piece of leakage accident condition information includes: acquiring a preset probability target value and a safety factor; determining a probability reference value according to the probability target value and the safety coefficient; and determining a target judgment result according to whether the occurrence probability corresponding to each leakage accident condition information is smaller than the probability reference value and whether the sum value is smaller than the probability target value.

In one embodiment, the determining the target judgment result according to whether the occurrence probability corresponding to each leakage accident condition information is smaller than a probability reference value and whether the sum value is smaller than a probability target value includes: if the occurrence probability corresponding to the leakage accident condition information is smaller than the probability reference value and the sum value is smaller than the probability target value, taking a first result as a target judgment result, wherein the first result indicates that the nuclear power plant meets the condition of actually eliminating early radioactive release or a large amount of radioactive release; and if the leakage accident condition information with the occurrence probability larger than or equal to the probability reference value exists in the leakage accident condition information, or the sum value is larger than or equal to the probability target value, taking a second result as a target judgment result, wherein the second result indicates that the nuclear power plant does not meet the condition of actually eliminating early radioactive release or a large amount of radioactive release.

The probability target value is used as a judgment value for judging whether the safety design of the nuclear power plant meets the requirement of actually eliminating early radioactive release or massive radioactive release; the probability benchmark value is used as a judgment value for judging whether each safety system and/or relief system in the nuclear power plant meets the requirement of actually eliminating early radioactive release or large amount of radioactive release.

Optionally, the probability target value and the safety factor are respectively input on the human-computer interaction interface, and the probability target value may be 10 ^-6 Pile-year, safety factor may be 10 ^-1 The terminal takes the product of the probability target value and the safety factor as a probability reference value, namely the probability reference value is 10 ^-7 Stacking and year, comparing the occurrence probability corresponding to each leakage accident condition information obtained in the step 3 with a probability reference value, adding the occurrence probabilities corresponding to all the leakage accident condition information to obtain a sum of the occurrence probability corresponding to each leakage accident condition information, comparing the sum with a probability target value, and finally enabling the occurrence probability corresponding to each leakage accident condition information to be smaller than the probability reference value, wherein the sum is smaller than the probability reference valueAnd taking the leakage accident condition information with the occurrence probability greater than or equal to the probability reference value in the leakage accident condition information as a first result, and taking the leakage accident condition information with the occurrence probability greater than or equal to the probability reference value or the sum greater than or equal to the probability target value as a second result, wherein the first result represents that the safety design of the nuclear power plant is qualified, and the second result represents that the safety design of the nuclear power plant is unqualified, so that the safety design needs to be carried out again. And when the second result appears, the terminal outputs all the leakage accident condition information corresponding to the probability of occurrence greater than or equal to the probability reference value, and the corresponding information of a safety system and/or a mitigation system and the like.

By changing the probability target value and the safety coefficient, the requirements of various safety design standards of the nuclear power plant can be flexibly met. In addition, only by inputting the probability target value and the safety factor, whether the safety design of the nuclear power plant is qualified or not, the leakage accident condition information corresponding to all the probability occurrence values which are more than or equal to the probability reference value, and a corresponding safety system and/or a release system can be obtained, so that the design defects of the nuclear power plant can be automatically identified, the time spent on the safety design analysis of the nuclear power plant is greatly reduced, and the accuracy of the safety design analysis of the nuclear power plant is improved.

In one embodiment, the method for analyzing the safety design of the nuclear power plant further includes: for each leakage accident condition information, judging and processing the leakage accident condition information to obtain the occurrence probability corresponding to the leakage accident condition information; wherein the judgment process includes at least one of a first judgment process and a second judgment process, wherein the first judgment process includes: inputting the leakage accident condition information into a preset nuclear power plant accident analysis program, and judging and processing the leakage accident condition information by the nuclear power plant accident analysis program based on the arrangement geometric information of the nuclear power plant, system equipment parameters and accident hypothesis; the second determination process includes: inputting the information of the leakage accident condition into a preset risk analysis program, constructing a PSA model based on the information of the leakage accident condition by the risk analysis program, and judging and processing the information of the leakage accident condition aiming at the PSA model.

The arrangement geometrical information of the nuclear power plant comprises position information of nuclear fuel, length, width and height of a stacked nuclear fuel container, position information of a radioactive barrier, position information of a safety system and/or a relief system and the like, system equipment parameters comprise a melting point, a specific heat capacity and the like of used materials, accident hypothesis comprises accident conditions caused by leakage accident conditions corresponding to leakage accident condition information, and design expansion conditions A are caused by DCH (design channel).

Optionally, the terminal performs different judgment processing according to different leakage accident condition information, performs first judgment processing on the leakage accident condition information which is simple and physically determined to occur or not to occur, performs second judgment processing on the leakage accident condition information which is complex and has a probability event occurring or not to occur, and determines whether to perform the first judgment processing or the second judgment processing on the leakage accident condition information according to experience by a professional or by using a trained training model in the terminal. The first judgment processing is based on design information of the nuclear power plant, such as arrangement geometric information of the nuclear power plant, system equipment parameters and accident hypothesis, leakage accident condition information and other accident conditions caused by the leakage accident condition are evaluated, and the occurrence probability corresponding to the leakage accident condition information in the nuclear power plant under the safety design is obtained. And the second judgment processing is based on the design information of the nuclear power plant, an event tree and a fault tree are constructed by using a risk analysis program RiskSpectrum, a complete PSA model is formed by combining data analysis, correlation analysis, human factor analysis and the like, the accident regulations and the system flow of the nuclear power plant are used as input, calculation is carried out through Boolean algebra, and finally the occurrence probability corresponding to the leakage accident condition information is obtained.

Optionally, the first judgment processing and the second judgment processing are respectively performed on the leakage accident condition information, the occurrence probability corresponding to the leakage accident condition information may be determined by the first judgment processing result and the second judgment processing result together, wherein the ratio of the first judgment processing result to the second judgment processing result may be determined as required, and is not limited herein.

The stress failure type is failure caused by breakthrough of ultimate stress and is originated from over-temperature and over-pressure of the containment, and the structural failure type is failure caused by loss of structural integrity and is originated from molten core penetration. Therefore, according to the fault type, the leakage accident condition information can be determined.

Optionally, the radioactive source information corresponds to at least one radioactive leakage path information, and one radioactive leakage path information corresponds to 2 fault types, so that one radioactive source information corresponds to a plurality of leakage accident condition information. For example, 1 radioactive source information and 8 radioactive leakage path information can obtain 16 leakage accident condition information.

And determining the leakage accident condition causing radioactivity leakage according to the fault type, thereby obtaining leakage accident condition information which may cause early radioactivity release or a large amount of radioactivity release in the nuclear power plant, and reducing the complexity of determining the leakage accident condition information.

In one embodiment, obtaining radioactive source information for a nuclear power plant includes: determining a radioactive component in the nuclear power plant according to the type of the nuclear power plant, wherein the radioactive component can generate radioactive release; and taking the position information of the radioactive part in the nuclear power plant as the radioactive source information.

Among them, the current nuclear power plants are classified into a pressurized water reactor nuclear power plant, a boiling water reactor nuclear power plant, a high temperature gas cooled reactor nuclear power plant, a heavy water reactor nuclear power plant, a pressure tube type graphite moderated boiling water reactor nuclear power plant, and a sodium cooled fast reactor nuclear power plant. The radioactive components generating radioactive release are different in each nuclear power plant, such as a pressurized water reactor nuclear power plant, the radioactive components are a reactor pressure vessel and a spent fuel pool, and the position information of the radioactive components is the radioactive source information. In the design stage of the nuclear power plant, the terminal can find the radioactive component according to the radioactive component identification in the design drawing of the nuclear power plant, and the radioactive source information is obtained according to the scale of the design drawing of the nuclear power plant and the geometric information of the radioactive component.

In a nuclear power plant, one or more radioactive shielding components are arranged in the radioactive component and the external environment, and the radioactive shielding components are used for controlling the radioactive release generated by the radioactive component in a certain area. The radioactive barrier components can exhibit a path for radioactivity to escape to the external environment due to overproof pressure, excessive temperature, etc., which is referred to as a radioactive leakage path.

Optionally, in a design stage of a nuclear power plant, the terminal may position the radioactive barrier component corresponding to the radioactive component according to the radioactive component identifier and the radioactive barrier identifier in the design drawing of the nuclear power plant, then determine at least one possible radioactive leakage path according to the radioactive component and the radioactive barrier component by using the training model, and obtain the radioactive leakage path information according to the scale of the design drawing of the nuclear power plant and the geometric information of the radioactive leakage path.

In one embodiment, after any of the above method embodiments is performed, when the safety design of the nuclear power plant is obtained to meet the requirement of actually eliminating early radioactive release or a large amount of radioactive release, possible operation and accident management should be adopted to reduce the risk of radioactive consequences as much as possible. Since the actual elimination of early radioactive emissions or of large radioactive emissions is not a simple probability cut-off, the risk and consequences of accidents should be minimized to the extent possible. Any design improvement, operation, accident management and the like which can reduce the accident risk and consequence should be practically applied in the nuclear power plant to ensure the public safety as much as possible. For example, flooding and spraying strategies for a Loss Of Coolant Accident (LOCA) in an interface loop in the nuclear power plant major Accident Management (SAMG) can reduce the release amount Of radioactive substances, thereby alleviating Accident consequences.

In summary, as shown in fig. 2, a flow chart of another method for analyzing a safety design of a nuclear power plant is provided, where a radioactive component in the nuclear power plant is determined according to a type of the nuclear power plant, the radioactive component may generate a radioactivity release, and location information of the radioactive component in the nuclear power plant is used as radioactivity source information. The method comprises the steps of determining a radioactive barrier component arranged between a radioactive component and the external environment in the nuclear power plant, determining a radioactive leakage path possibly occurring in the radioactive barrier component, and taking the position information of the radioactive leakage path in the radioactive barrier component as radioactive leakage path information. Determining the fault type of radioactive leakage, wherein the fault type comprises a stress failure type and a structural failure type, constructing a plurality of different leakage accident working conditions according to the radioactive source information and the radioactive leakage path information and the fault type, and acquiring a plurality of different leakage accident working condition information according to the constructed plurality of different leakage accident working conditions. The method comprises the steps of identifying and combing the safety system and/or the relieving system for preventing each leakage accident working condition from a preset database of a plurality of safety systems and/or relieving systems designed aiming at various leakage accident working conditions of the nuclear power plant in advance, and determining the safety system and/or the relieving system corresponding to each leakage accident working condition. For each leakage accident condition information, judging and processing the leakage accident condition information to obtain the occurrence probability corresponding to the leakage accident condition information; wherein the judgment process includes at least one of a first judgment process and a second judgment process, wherein the first judgment process includes: inputting the leakage accident condition information into a preset nuclear power plant accident analysis program, and judging and processing the leakage accident condition information by the nuclear power plant accident analysis program based on the arrangement geometric information of the nuclear power plant, system equipment parameters and accident hypothesis; the second determination process includes: and inputting the leakage accident condition information into a preset risk analysis program, so that a PSA (pressure swing adsorption) model is constructed by the risk analysis program based on the leakage accident condition information, and the leakage accident condition information is judged and processed aiming at the PSA model. Acquiring a preset probability target value and a preset safety factor, determining a probability reference value according to the probability target value and the safety factor, and taking a first result as a target judgment result if the occurrence probability corresponding to each leakage accident condition information is smaller than the probability reference value and the sum value is smaller than the probability target value, wherein the first result indicates that the nuclear power plant meets the condition of actually eliminating early radioactivity release or a large amount of radioactivity release; and if the leakage accident condition information with the occurrence probability larger than or equal to the probability reference value exists in the leakage accident condition information, or the sum value is larger than or equal to the probability target value, taking a second result as a target judgment result, wherein the second result indicates that the nuclear power plant does not meet the condition of actually eliminating early radioactive release or a large amount of radioactive release, and design improvement is needed.

It should be understood that, although the steps in the flowcharts related to the embodiments as described above are sequentially displayed as indicated by arrows, the steps are not necessarily performed sequentially as indicated by the arrows. The steps are not performed in the exact order shown and described, and may be performed in other orders, unless explicitly stated otherwise. Moreover, at least a part of the steps in the flowcharts related to the embodiments described above may include multiple steps or multiple stages, which are not necessarily performed at the same time, but may be performed at different times, and the execution order of the steps or stages is not necessarily sequential, but may be performed alternately or alternately with other steps or at least a part of the steps or stages in other steps.

Based on the same inventive concept, the embodiment of the application also provides a nuclear power plant safety design analysis device for realizing the nuclear power plant safety design analysis method. The implementation scheme for solving the problem provided by the device is similar to the implementation scheme recorded in the method, so specific limitations in one or more embodiments of the nuclear power plant safety design analysis device provided below can be referred to as the limitations on the nuclear power plant safety design analysis method in the foregoing, and details are not described here again.

In one embodiment, as shown in FIG. 3, there is provided a nuclear power plant safety design analysis device 300, comprising: a first obtaining module 301, a first determining module 302, a second determining module 303, and a second obtaining module, wherein:

the first obtaining module 301 is configured to obtain radioactive source information of a nuclear power plant, and obtain radioactive leakage path information of the nuclear power plant.

The first determining module 302 is configured to determine a plurality of different leakage accident condition information according to the radioactivity source information and the radioactivity leakage path information.

And a second determining module 303, configured to determine occurrence probabilities corresponding to the leakage accident condition information.

A second obtaining module 304, configured to obtain a target judgment result for the nuclear power plant based on the occurrence probability corresponding to each leakage accident condition information and the sum of the occurrence probabilities corresponding to each leakage accident condition information, where the target judgment result is used to indicate whether the nuclear power plant meets a condition for actually eliminating early radioactive release or a condition for releasing a large amount of radioactive release.

In one embodiment, the second obtaining module 304 is further configured to obtain a preset probability target value and a safety factor; determining a probability reference value according to the probability target value and the safety factor; and determining a target judgment result according to whether the occurrence probability corresponding to the leakage accident condition information is smaller than the probability reference value and whether the sum value is smaller than the probability target value.

In one embodiment, the second obtaining module 304 is further configured to, if the occurrence probability corresponding to each leakage accident condition information is smaller than the probability reference value and the sum value is smaller than the probability target value, take a first result as a target judgment result, where the first result indicates that the nuclear power plant meets a condition of actually eliminating early radioactivity release or a large amount of radioactivity release; and if the leakage accident condition information with the occurrence probability larger than or equal to the probability reference value exists in the leakage accident condition information, or the sum value is larger than or equal to the probability target value, taking a second result as a target judgment result, wherein the second result indicates that the nuclear power plant does not meet the condition of actually eliminating early radioactive release or a large amount of radioactive release.

In one embodiment, the second determining module 303 is further configured to, for each leakage accident condition information, perform judgment processing on the leakage accident condition information to obtain an occurrence probability corresponding to the leakage accident condition information; wherein the judgment process includes at least one of a first judgment process and a second judgment process, wherein the first judgment process includes: inputting the leakage accident condition information into a preset nuclear power plant accident analysis program, and judging and processing the leakage accident condition information by the nuclear power plant accident analysis program based on the arrangement geometric information of the nuclear power plant, system equipment parameters and accident hypothesis; the second determination process includes: inputting the information of the leakage accident condition into a preset risk analysis program, constructing a PSA model based on the information of the leakage accident condition by the risk analysis program, and judging and processing the information of the leakage accident condition aiming at the PSA model.

In one embodiment, the first determining module 302 is further configured to determine a failure type of the radioactive leakage, where the failure type includes a stress failure type and a structural failure type; according to the radioactive source information and the radioactive leakage path information, a plurality of different leakage accident working conditions are constructed according to the fault types, and a plurality of different leakage accident working condition information are obtained according to the constructed plurality of different leakage accident working conditions.

In one embodiment, the first obtaining module 301 is further configured to determine a radioactive component in the nuclear power plant according to a type of the nuclear power plant, where the radioactive component may generate a radioactive release; and taking the position information of the radioactive component in the nuclear power plant as the radioactive source information.

In one embodiment, the first obtaining module 301 is further configured to determine a radioactive barrier component disposed between a radioactive component in the nuclear power plant and an external environment; and determining a possible radioactive leakage path in the radioactive barrier component, and using the position information of the radioactive leakage path in the radioactive barrier component as the radioactive leakage path information.

All or part of each module in the nuclear power plant safety design analysis device can be realized through software, hardware and a combination thereof. The modules can be embedded in a hardware form or independent from a processor in the computer device, and can also be stored in a memory in the computer device in a software form, so that the processor can call and execute operations corresponding to the modules.

In one embodiment, a computer device is provided, which may be a terminal, and its internal structure diagram may be as shown in fig. 4. The computer apparatus includes a processor, a memory, an input/output interface, a communication interface, a display unit, and an input device. The processor, the memory and the input/output interface are connected by a system bus, and the communication interface, the display unit and the input device are connected by the input/output interface to the system bus. Wherein the processor of the computer device is configured to provide computing and control capabilities. The memory of the computer device includes a non-volatile storage medium and an internal memory. The non-volatile storage medium stores an operating system and a computer program. The internal memory provides an environment for the operation of an operating system and computer programs in the non-volatile storage medium. The input/output interface of the computer device is used for exchanging information between the processor and an external device. The communication interface of the computer device is used for communicating with an external terminal in a wired or wireless manner, and the wireless manner can be realized through WIFI, a mobile cellular network, NFC (near field communication) or other technologies. The computer program is executed by a processor to implement a nuclear power plant safety design analysis method. The display unit of the computer device is used for forming a visual visible picture, and can be a display screen, a projection device or a virtual reality imaging device. The display screen can be a liquid crystal display screen or an electronic ink display screen, and the input device of the computer equipment can be a touch layer covered on the display screen, a key, a track ball or a touch pad arranged on the shell of the computer equipment, an external keyboard, a touch pad or a mouse and the like.

It will be appreciated by those skilled in the art that the configuration shown in fig. 4 is a block diagram of only a portion of the configuration associated with the present application, and is not intended to limit the computing device to which the present application may be applied, and that a particular computing device may include more or fewer components than shown, or may combine certain components, or have a different arrangement of components.

In one embodiment, a computer device is further provided, which includes a memory and a processor, the memory stores a computer program, and the processor implements the steps of the above method embodiments when executing the computer program.

In an embodiment, a computer-readable storage medium is provided, on which a computer program is stored which, when being executed by a processor, carries out the steps of the above-mentioned method embodiments.

In an embodiment, a computer program product is provided, comprising a computer program which, when being executed by a processor, carries out the steps of the above-mentioned method embodiments.

It will be understood by those skilled in the art that all or part of the processes of the methods of the embodiments described above can be implemented by hardware instructions of a computer program, which can be stored in a non-volatile computer-readable storage medium, and when executed, can include the processes of the embodiments of the methods described above. Any reference to memory, database, or other medium used in the embodiments provided herein may include at least one of non-volatile and volatile memory. The nonvolatile Memory may include Read-Only Memory (ROM), magnetic tape, floppy disk, flash Memory, optical Memory, high-density embedded nonvolatile Memory, resistive Random Access Memory (ReRAM), magnetic Random Access Memory (MRAM), ferroelectric Random Access Memory (FRAM), phase Change Memory (PCM), graphene Memory, and the like. Volatile Memory can include Random Access Memory (RAM), external cache Memory, and the like. By way of illustration and not limitation, RAM can take many forms, such as Static Random Access Memory (SRAM) or Dynamic Random Access Memory (DRAM), for example. The databases referred to in various embodiments provided herein may include at least one of relational and non-relational databases. The non-relational database may include, but is not limited to, a block chain based distributed database, and the like. The processors referred to in the embodiments provided herein may be general purpose processors, central processing units, graphics processors, digital signal processors, programmable logic devices, quantum computing based data processing logic devices, etc., without limitation.

The technical features of the above embodiments can be arbitrarily combined, and for the sake of brevity, all possible combinations of the technical features in the above embodiments are not described, but should be considered as the scope of the present specification as long as there is no contradiction between the combinations of the technical features.

The above-mentioned embodiments only express several embodiments of the present application, and the description thereof is specific and detailed, but not construed as limiting the scope of the present application. It should be noted that, for a person skilled in the art, several variations and modifications can be made without departing from the concept of the present application, and these are all within the scope of protection of the present application. Therefore, the protection scope of the present application should be subject to the appended claims.

Claims

1. A nuclear power plant safety design analysis method, the method comprising:

the method comprises the steps of obtaining radioactive source information of a nuclear power plant and obtaining radioactive leakage path information of the nuclear power plant;

determining a plurality of different leakage accident condition information according to the radioactive source information and the radioactive leakage path information;

determining the occurrence probability corresponding to each leakage accident condition information;

and acquiring a target judgment result aiming at the nuclear power plant based on the occurrence probability corresponding to each leakage accident condition information and the sum of the occurrence probabilities corresponding to each leakage accident condition information, wherein the target judgment result is used for indicating whether the nuclear power plant meets the condition of actually eliminating early radioactive release or a large amount of radioactive release.

2. The method of claim 1, wherein obtaining a target judgment result for the nuclear power plant based on the occurrence probability corresponding to each piece of leakage accident condition information and the sum of the occurrence probabilities corresponding to each piece of leakage accident condition information comprises:

acquiring a preset probability target value and a safety factor;

determining a probability reference value according to the probability target value and the safety factor;

and determining the target judgment result according to whether the occurrence probability corresponding to each leakage accident condition information is smaller than the probability reference value and whether the sum value is smaller than the probability target value.

3. The method according to claim 2, wherein the determining the target judgment result according to whether the occurrence probability corresponding to each leakage accident condition information is smaller than the probability reference value and whether the sum value is smaller than the probability target value comprises:

if the occurrence probability corresponding to each leakage accident condition information is smaller than the probability reference value and the sum value is smaller than the probability target value, taking a first result as the target judgment result, wherein the first result indicates that the nuclear power plant meets the condition of actually eliminating early radioactive release or massive radioactive release;

and if the leakage accident condition information with the occurrence probability larger than or equal to the probability reference value exists in each leakage accident condition information, or the sum value is larger than or equal to the probability target value, taking a second result as the target judgment result, wherein the second result indicates that the nuclear power plant does not meet the condition of actually eliminating early radioactive release or a large amount of radioactive release.

4. The method of claim 1, further comprising:

for each leakage accident condition information, judging and processing the leakage accident condition information to obtain the occurrence probability corresponding to the leakage accident condition information;

wherein the judgment process includes at least one of a first judgment process and a second judgment process, wherein the first judgment process includes: inputting the leakage accident condition information into a preset nuclear power plant accident analysis program, and judging and processing the leakage accident condition information by the nuclear power plant accident analysis program based on the arrangement geometric information of the nuclear power plant, system equipment parameters and accident hypothesis;

the second determination process includes: inputting the leakage accident condition information into a preset risk analysis program, constructing a PSA (pressure swing adsorption) model by the risk analysis program based on the leakage accident condition information, and judging and processing the leakage accident condition information according to the PSA model.

5. The method of claim 1, wherein said determining a plurality of different leakage incident condition information based on said radioactivity source information and said radioactivity leakage pathway information comprises:

determining the fault type of radioactive leakage, wherein the fault type comprises a stress failure type and a structural failure type;

and constructing a plurality of different leakage accident working conditions according to the radioactive source information and the radioactive leakage path information and the fault type, and acquiring the plurality of different leakage accident working condition information according to the constructed plurality of different leakage accident working conditions.

6. The method of claim 1, wherein the obtaining radioactive source information of the nuclear power plant comprises:

determining a radioactive component in the nuclear power plant according to the type of the nuclear power plant, the radioactive component being capable of generating a radioactive release;

and using the position information of the radioactive component in the nuclear power plant as the radioactive source information.

7. The method of claim 1, wherein the obtaining the radioactive leakage path information of the nuclear power plant comprises:

determining a radioactive barrier component disposed between a radioactive component in the nuclear power plant and an external environment;

and determining a possible radioactive leakage path in the radioactive barrier component, and using the position information of the radioactive leakage path in the radioactive barrier component as the radioactive leakage path information.

8. A nuclear power plant safety design analysis device, the device comprising:

the system comprises a first acquisition module, a second acquisition module and a third acquisition module, wherein the first acquisition module is used for acquiring radioactive source information of a nuclear power plant and acquiring radioactive leakage path information of the nuclear power plant;

the first determining module is used for determining a plurality of different leakage accident condition information according to the radioactive source information and the radioactive leakage path information;

the second determining module is used for determining the occurrence probability corresponding to each leakage accident working condition information;

and the second acquisition module is used for acquiring a target judgment result aiming at the nuclear power plant based on the occurrence probability corresponding to each piece of leakage accident condition information and the sum value of the occurrence probabilities corresponding to each piece of leakage accident condition information, wherein the target judgment result is used for indicating whether the nuclear power plant meets the condition of actually eliminating early radioactive release or a large amount of radioactive release.

9. A computer device comprising a memory and a processor, the memory storing a computer program, characterized in that the processor, when executing the computer program, implements the steps of the method of any of claims 1 to 7.

10. A computer-readable storage medium, on which a computer program is stored which, when being executed by a processor, carries out the steps of the method according to any one of claims 1 to 7.

11. A computer program product comprising a computer program, characterized in that the computer program realizes the steps of the method of any one of claims 1 to 7 when executed by a processor.