CN111863296B - Risk guidance-based simulation method and system for safety injection system of nuclear power plant - Google Patents
Risk guidance-based simulation method and system for safety injection system of nuclear power plant Download PDFInfo
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- CN111863296B CN111863296B CN202010811999.3A CN202010811999A CN111863296B CN 111863296 B CN111863296 B CN 111863296B CN 202010811999 A CN202010811999 A CN 202010811999A CN 111863296 B CN111863296 B CN 111863296B
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Abstract
The invention discloses a risk guidance-based simulation method and system for a safety injection system of a nuclear power plant, wherein the method identifies a minimum cut set of functional requirements of the safety injection system through a determinism and determines an implementation principle, a system setting and an operation mode of the safety injection system; the weak links of the safety injection system are identified through probability theory, the importance of different design schemes of the safety injection system on the safety of a nuclear power plant is determined, and system combination in the design of the safety injection system is provided to provide optimization suggestions. The invention comprehensively analyzes the deterministic theory and the probabilistic theory to form a set of safe injection system design method taking risk guide as guidance, realizes the aims of minimizing the setting of the safe injection system and maximizing the safety performance, ensures the safety of the nuclear power plant and further optimizes the construction cost of the nuclear power plant.
Description
Technical Field
The invention relates to the technical field of safety design of nuclear power plants, in particular to a method and a system for simulating a safety injection system of a nuclear power plant based on risk guidance.
Background
After a pressurized water reactor nuclear power plant has a reactor coolant pipeline break accident (LOCA), the reactor coolant is lost from a pressure vessel, so that a reactor core fuel element loses the coolant and is burnt, and the safety performance of the reactor is further threatened; or when the reactor rod control regulating system cannot work, the reactor core fuel elements are burnt out due to overhigh power caused by the loss of control of reactivity, and the safety performance of the reactor is further threatened. Therefore, it is necessary to provide a safety injection system for the core reactivity control and the LOCA accident to cope with the core reactivity control when the rod control system cannot be adjusted and to cope with the loss of the core coolant in the LOCA accident.
The design of the traditional safety injection system is mainly based on the cognition of a determinism, the safety injection water quantity requirement aiming at the LOCA accident and the boron concentration requirement aiming at the main steam pipeline rupture accident under the thermal shutdown propose design requirements on the safety injection system, but the optimization configuration of the safety injection system is not considered, so that the safety injection system designed by the existing design method cannot achieve the function maximization and the setting optimization.
Therefore, a design method of a safety injection system of a nuclear power plant guided by risks is provided, which is used for designing the safety injection system so as to achieve the purposes of maximizing functions and optimizing settings.
Disclosure of Invention
The invention provides a risk guidance-based simulation method for a safety injection system of a nuclear power plant, which is used for designing the safety injection system so as to achieve the purposes of maximizing functions and optimizing settings and improve the reliability of design.
The invention is realized by the following technical scheme:
a risk guidance-based simulation method for a safe injection system of a nuclear power plant comprises the following steps:
step one, identifying accidents of a nuclear power plant requiring a safe injection function;
analyzing restrictive requirements of different accidents on safe injection flow and boron concentration, and determining a minimum cut set of functional requirements of a safe injection system;
step three, forming a primary design scheme of the safety injection system according to the functional requirements of the safety injection system;
step four, establishing a fault tree model of the safety injection system according to a primary design scheme of the safety injection system, analyzing weak links set by the safety injection system and giving optimization suggestions;
establishing a nuclear power plant event tree model, analyzing the influence of different failure rates of the safety injection system on the damage frequency of the reactor core, and giving an optimization suggestion;
and step six, based on the optimization suggestions of the step four and the step five, carrying out re-optimization design on the safety injection system, then carrying out iterative analysis by combining the accident analysis of the step two, and finally determining the optimization design scheme of the safety injection system.
Optionally, the accidents of the nuclear power plant requiring the safety injection function, which are identified in the first step of the present invention, include design benchmark accidents and design extension accidents of the nuclear power plant, including reactor coolant pipeline break accidents, main steam pipeline break accidents and transient faults of unexpected shutdown.
Optionally, in the second step of the present invention, a deterministic analysis method is adopted to perform quantitative analysis on accidents with requirements of the safety injection system, to determine restrictive requirements on the safety injection flow and the boron concentration under different accident conditions, respectively, and to analyze the influence of the false input of the safety injection system, to determine the maximum restrictive requirement on the safety injection flow, and to determine the minimum cut set of the functional requirements of the safety injection system, including the minimum requirements on the high, medium, and low pressure safety injection flows, and the minimum and maximum restrictive requirements on the high pressure injection flow, the maximum boron concentration, and the like.
Optionally, the method for analyzing the safety injection system fault tree model quantitatively comprises the following steps of: the frequency of primary safety injection system failures is noted as f0Analyzing the failure rate of each component of the safety injection system, which is increased to cause the failure rate of the safety injection system, and recording the failure frequency of the safety injection system as f1And then:
a larger value of r indicates that this component is more important for a safety injection system, and when r is larger than a preset value, the function of this component should be optimally set.
Optionally, the fifth step of the present invention is to perform quantitative analysis on the event tree model of the nuclear power plant by using a probability theory method: identifying event sequences of the safety injection system in the event tree sequence, and analyzing the core damage frequency CDF of the event sequences corresponding to different failure frequencies of the safety injection systemiAnd total core damage CDF of nuclear power planttDetermining a combination of passive and active modes of the safety injection system and determining an optimization recommendation for the column number setting.
On the other hand, the invention also provides a nuclear power plant safety injection system simulation system based on risk guidance, which comprises a determinacy analysis module, a probability theory analysis module and an optimization module;
the determinant analysis module is used for identifying accidents of the nuclear power plant requiring a safe injection function; analyzing restrictive requirements of different accidents on safe injection flow and boron concentration, and determining a minimum cut set of functional requirements of a safe injection system; forming a primary safety injection system design scheme according to the functional requirements of the safety injection system;
the probability theory analysis module is used for establishing a fault tree model of the safe injection system according to a primary safe injection system design scheme, analyzing weak links set by the safe injection system and outputting an optimization suggestion; establishing a nuclear power plant event tree model, analyzing the influence of different failure rates of a safety injection system on the damage frequency of the reactor core and outputting an optimization suggestion;
the optimization module obtains the optimization suggestion output by the probability theory analysis module, carries out re-optimization design on the safety injection system, then carries out iterative analysis by combining the accident analysis of the determinism analysis module, and finally determines and outputs the optimization design scheme of the safety injection system.
Optionally, the accidents of the nuclear power plant requiring the safe injection function, which are identified by the determinism analysis module of the invention, include design benchmark accidents and design extension accidents of the nuclear power plant, including reactor coolant pipeline break accidents, main steam pipeline break accidents and transient faults of failure to expect shutdown.
Optionally, the deterministic analysis module of the present invention performs quantitative analysis on the accident with the demand of the safety injection system by using a deterministic analysis method, determines the restrictive requirements on the safety injection flow and the boron concentration under different accident conditions, analyzes the influence of the false input of the safety injection system, determines the maximum restrictive requirement on the safety injection flow, and determines the minimum cut set of the functional requirements of the safety injection system, including the minimum requirements on the high, medium, and low pressure safety injection flows, and the minimum and maximum restrictive requirements on the maximum flow limit of the high pressure injection and the minimum and maximum restrictive requirements on the boron concentration.
Optionally, the probability theory analysis module of the invention performs quantitative analysis on the safety injection system fault tree model by using a probability theory analysis method: the frequency of primary safety injection system failures is noted as f0Analyzing the failure rate of each component of the safety injection system, which is increased to cause the failure rate of the safety injection system, and recording the failure frequency of the safety injection system as f1And then:
a larger value of r indicates that this component is more important for a safety injection system, and when r is larger than a preset value, the function of this component should be optimally set.
Optionally, the probability theory analysis module of the present invention performs quantitative analysis on the event tree model of the nuclear power plant by using a probability theory method: identifying event sequences of the safety injection system in the event tree sequence, and analyzing the core damage frequency CDF of the event sequences corresponding to different failure frequencies of the safety injection systemiAnd total core damage CDF of nuclear power planttDetermining a combination of passive and active modes of the safety injection system and determining an optimization recommendation for the column number setting.
The invention has the following advantages and beneficial effects:
1. according to the invention, a risk guidance simulation method is adopted, the design requirements and the functions of the safety injection system and other aspects are comprehensively considered to carry out the simulation design of the safety injection system, the minimization of the setting of the safety injection system and the maximization of the safety function can be realized, the optimized design scheme of the safety injection system is obtained, and the optimized design of the safety injection system is realized based on the optimized design scheme, so that the safety and the economy of a nuclear power plant are improved.
2. The invention has wide application range, and is particularly suitable for the design of a safe injection system of a small pressurized water reactor nuclear power plant.
Drawings
The accompanying drawings, which are included to provide a further understanding of the embodiments of the invention and are incorporated in and constitute a part of this application, illustrate embodiment(s) of the invention and together with the description serve to explain the principles of the invention. In the drawings:
FIG. 1 is a schematic flow chart of the method of the present invention.
Fig. 2 is a schematic diagram of the system architecture of the present invention.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is further described in detail below with reference to examples and accompanying drawings, and the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not meant to limit the present invention.
Example 1
Compared with the traditional design of the safety injection system based on the deterministic theory, the embodiment comprehensively considers all accident conditions of the safety injection system, and provides the simulation method of the safety injection system of the nuclear power plant based on risk guidance by combining the function optimization of the safety injection system by the probabilistic theory method.
The method of the embodiment is mainly used for maintaining the water content and the reactivity of the reactor under the accident condition and ensuring the safety of the reactor. The design starts from realizing the main functions of the injection system, is based on determinacy analysis, takes risk guidance as guidance and establishes a complete design method of the safe injection system.
As shown in fig. 1, the method of the present embodiment includes the following steps:
1. design benchmark accidents and design extension conditions of a nuclear power plant with requirements on a safe injection system are identified, such as large, medium and small LOCA accidents, main steam pipeline breakage accidents (MSLB), transient conditions of unexpected shutdown (ATWT) and the like.
2. The method comprises the steps of carrying out quantitative analysis on accidents with requirements of a safety injection system by adopting a determinacy analysis method, determining minimum requirements and boron concentration requirements on the safety injection flow under different accident working conditions, analyzing the influence of mistaken investment of the safety injection system, determining the maximum limiting requirement of the safety injection flow, and determining the minimum cut set of functional requirements of the safety injection system, such as the minimum requirements on high, medium and low pressure safety injection flows, the maximum flow limit on high pressure injection, the minimum boron concentration requirement of a boric acid solution and the like.
3. Forming a primary safety injection system design scheme according to the functional requirements of the safety injection system, and determining a passive or active safety injection realization principle according to the safety flow requirement; determining the connection conditions and connection modes of high, medium and low pressure safe injection according to the initial state and the accident process which are possible to happen; considering single failure of the system, the redundant design of the redundant system is considered, such as arranging 2 columns or 3 columns of safe injection systems, and the like.
4. Establishing a preliminary safe injection system fault tree model according to a preliminary safe injection system design scheme, and carrying out quantitative analysis on the preliminary safe injection system fault tree model by adopting a probability theory analysis method: the frequency of primary safety injection system failures is noted as f0Analyzing the failure rate of each component of the safety injection system, which is increased to cause the failure rate of the safety injection system, and recording the failure frequency of the safety injection system as f1And then:
a larger value of r indicates that this component is more important for a safety injection system, and when r is larger than a preset value, the function of this component should be optimally set.
5. Establishing an event tree model of the nuclear power plant, and carrying out quantitative analysis on the event tree model of the nuclear power plant by adopting a probability theory analysis method: identifying a sequence of events in the sequence of events for which a safety injection system is to be used, analyzing the frequency of failure of the safety injection system as a function of the frequency of core damage in the sequence of events, CDFiAnd total core damage CDF of nuclear power planttDetermining the combination mode of the passive and active of the safe injection system, determining the number of columns and setting and other optimization design suggestions.
6. According to the quantitative analysis suggestion of the probability theory, the safe injection system is re-optimized and designed, finally, iterative analysis is carried out by combining the accident analysis of the deterministic theory, and finally, the implementation principle, the system setting and the operation mode of the safe injection system are determined, so that the system design is optimized.
The safety injection system is designed according to the optimized safety injection system optimization design scheme obtained by the simulation method of the embodiment, the aims of minimizing the setting of the safety injection system and maximizing the safety performance are achieved, the safety of the nuclear power plant is guaranteed, and meanwhile the construction cost of the nuclear power plant is further optimized.
Example 2
Based on the simulation method provided in the above embodiment 1, as shown in fig. 2, the embodiment provides a risk guidance-based simulation system for a safe injection system of a nuclear power plant, which includes a deterministic theory analysis module, a probabilistic theory analysis module, and an optimization module.
The system comprises a determinism analysis module, a safety injection module and a safety injection module, wherein the determinism analysis module is used for identifying accidents of a nuclear power plant requiring a safety injection function; analyzing restrictive requirements of different accidents on safe injection flow and boron concentration, and determining a minimum cut set of functional requirements of a safe injection system; forming a primary safety injection system design scheme according to the functional requirements of the safety injection system;
the probability theory analysis module is used for establishing a fault tree model of the safe injection system according to a primary safe injection system design scheme, analyzing weak links set by the safe injection system and outputting optimization suggestions; establishing a nuclear power plant event tree model, analyzing the influence of different failure rates of a safety injection system on the damage frequency of the reactor core and outputting an optimization suggestion;
the optimization module obtains the optimization suggestion output by the probability theory analysis module, carries out re-optimization design on the safety injection system, then carries out iterative analysis by combining with the accident analysis of the determinism analysis module, and finally determines and outputs the optimization design scheme of the safety injection system.
The accidents of the nuclear power plant requiring the safe injection function, which are identified by the determinism analysis module, of the embodiment include design benchmark accidents and design extension accidents of the nuclear power plant, including reactor coolant pipeline breakage accidents, main steam pipeline breakage accidents and transient faults of unexpected shutdown.
The determinacy analysis module of the embodiment performs quantitative analysis on accidents with requirements of the safety injection system by using a determinacy analysis method, determines restrictive requirements on the safety injection flow and the boron concentration under different accident conditions, analyzes the influence of mistaken investment of the safety injection system, determines the maximum restrictive requirement on the safety injection flow, and determines the minimum cut set of the functional requirements of the safety injection system, including the minimum requirements on high, medium and low pressure safety injection flows, and the minimum and maximum restrictive requirements on the maximum flow limit of high pressure injection and the minimum and maximum restrictive requirements on the boron concentration.
Probability theory analysis module of the embodimentCarrying out quantitative analysis on the fault tree model of the safety injection system by adopting a probability theory analysis method: the frequency of primary safety injection system failures is noted as f0Analyzing the failure rate of each component of the safety injection system, which is increased to cause the failure rate of the safety injection system, and recording the failure frequency of the safety injection system as f1And then:
a larger value of r indicates that this component is more important for a safety injection system, and when r is larger than a preset value, the function of this component should be optimally set.
The probability theory analysis module of the embodiment performs quantitative analysis on the event tree model of the nuclear power plant by adopting a probability theory method: identifying event sequences of the safety injection system in the event tree sequence, and analyzing the core damage frequency CDF of the event sequences corresponding to different failure frequencies of the safety injection systemiAnd total core damage CDF of nuclear power planttDetermining a combination of passive and active modes of the safety injection system and determining an optimization recommendation for the column number setting.
The safety injection system is designed according to the optimized safety injection system optimization design scheme obtained by the simulation system of the embodiment, the goals of minimizing the setting of the safety injection system and maximizing the safety performance are achieved, the safety of the nuclear power plant is guaranteed, and meanwhile the construction cost of the nuclear power plant is further optimized.
As will be appreciated by one skilled in the art, embodiments of the present application may be provided as a method, system, or computer program product. Accordingly, the present application may take the form of an entirely hardware embodiment, an entirely software embodiment or an embodiment combining software and hardware aspects. Furthermore, the present application may take the form of a computer program product embodied on one or more computer-usable storage media (including, but not limited to, disk storage, CD-ROM, optical storage, and the like) having computer-usable program code embodied therein.
The present application is described with reference to flowchart illustrations and/or block diagrams of methods, apparatus (systems), and computer program products according to embodiments of the application. It will be understood that each flow and/or block of the flow diagrams and/or block diagrams, and combinations of flows and/or blocks in the flow diagrams and/or block diagrams, can be implemented by computer program instructions. These computer program instructions may be provided to a processor of a general purpose computer, special purpose computer, embedded processor, or other programmable data processing apparatus to produce a machine, such that the instructions, which execute via the processor of the computer or other programmable data processing apparatus, create means for implementing the functions specified in the flowchart flow or flows and/or block diagram block or blocks.
These computer program instructions may also be stored in a computer-readable memory that can direct a computer or other programmable data processing apparatus to function in a particular manner, such that the instructions stored in the computer-readable memory produce an article of manufacture including instruction means which implement the function specified in the flowchart flow or flows and/or block diagram block or blocks.
These computer program instructions may also be loaded onto a computer or other programmable data processing apparatus to cause a series of operational steps to be performed on the computer or other programmable apparatus to produce a computer implemented process such that the instructions which execute on the computer or other programmable apparatus provide steps for implementing the functions specified in the flowchart flow or flows and/or block diagram block or blocks.
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are merely exemplary embodiments of the present invention, and are not intended to limit the scope of the present invention, and any modifications, equivalent substitutions, improvements and the like made within the spirit and principle of the present invention should be included in the scope of the present invention.
Claims (6)
1. A risk guidance-based simulation method for a safe injection system of a nuclear power plant is characterized by comprising the following steps:
step one, identifying accidents of a nuclear power plant requiring a safe injection function;
analyzing restrictive requirements of different accidents on safe injection flow and boron concentration, and determining a minimum cut set of functional requirements of a safe injection system;
step three, forming a primary design scheme of the safety injection system according to the functional requirements of the safety injection system; step four, establishing a fault tree model of the safety injection system according to a primary design scheme of the safety injection system, analyzing weak links set by the safety injection system and giving optimization suggestions;
and fourthly, carrying out quantitative analysis on the fault tree model of the safety injection system by adopting a probability theory analysis method: the frequency of primary safety injection system failures is noted as f0Analyzing the failure rate of each component of the safety injection system, which is increased to cause the failure rate of the safety injection system, and recording the failure frequency of the safety injection system as f1And then:
the larger the value of r is, the more important the component is for a safe injection system, and when r is larger than a preset value, the function of the component should be optimally set;
establishing a nuclear power plant event tree model, analyzing the influence of different failure rates of the safety injection system on the damage frequency of the reactor core, and giving an optimization suggestion;
and fifthly, carrying out quantitative analysis on the nuclear power plant event tree model by adopting a probability theory method: identifying event sequences of the safety injection system in the event tree sequence, and analyzing the core damage frequency CDF of the event sequences corresponding to different failure frequencies of the safety injection systemiAnd total core damage CDF of nuclear power planttDetermining a passive and active combination mode of the safe injection system and determining an optimization suggestion of the column number setting;
and step six, based on the optimization suggestions of the step four and the step five, carrying out re-optimization design on the safety injection system, then carrying out iterative analysis by combining the accident analysis of the step two, and finally determining the optimization design scheme of the safety injection system.
2. The risk guidance-based nuclear power plant safety injection system simulation method according to claim 1, wherein the accidents of the nuclear power plant, which are identified in the step one, requiring safety injection function comprise design benchmark accidents and design extension accidents of the nuclear power plant, including reactor coolant pipeline breakage accidents, main steam pipeline breakage accidents and transient faults of failure to expect shutdown.
3. The method for simulating the safety injection system of the nuclear power plant based on the risk guidance as claimed in claim 1, wherein in the second step, quantitative analysis is performed on accidents requiring the safety injection system by using a determinism analysis method, restrictive requirements on the safety injection flow and the boron concentration under different accident conditions are determined, the influence of mistaken investment of the safety injection system is analyzed, the maximum restrictive requirement on the safety injection flow is determined, and the minimum cut set of the functional requirements of the safety injection system is determined, including the minimum requirements on the high, medium and low pressure safety injection flows, the maximum flow limit on the high pressure injection and the minimum and maximum restrictive requirements on the boron concentration.
4. A nuclear power plant safety injection system simulation system based on risk guidance is characterized by comprising a determinacy analysis module, a probability theory analysis module and an optimization module;
the determinant analysis module is used for identifying accidents of the nuclear power plant requiring a safe injection function; analyzing restrictive requirements of different accidents on safe injection flow and boron concentration, and determining a minimum cut set of functional requirements of a safe injection system; forming a primary design scheme of the safety injection system according to the functional requirements of the safety injection system; the probability theory analysis module is used for establishing a fault tree model of the safe injection system according to a primary safe injection system design scheme, analyzing weak links set by the safe injection system and outputting an optimization suggestion; establishing a nuclear power plant event tree model, analyzing the influence of different failure rates of a safety injection system on the damage frequency of the reactor core and outputting an optimization suggestion;
the probability theory analysis module carries out quantitative analysis on the safety injection system fault tree model by adopting a probability theory analysis method: the frequency of primary safety injection system failures is noted as f0Analyzing the failure rate of each component of the safety injection system, which is increased to cause the failure rate of the safety injection system, and recording the failure frequency of the safety injection system as f1And then:
the larger the value of r is, the more important the component is for a safe injection system, and when r is larger than a preset value, the function of the component should be optimally set;
the probability theory analysis module carries out quantitative analysis on the nuclear power plant event tree model by adopting a probability theory method: identifying event sequences of the safety injection system in the event tree sequence, and analyzing the core damage frequency CDF of the event sequences corresponding to different failure frequencies of the safety injection systemiAnd total core damage CDF of nuclear power planttDetermining a passive and active combination mode of the safe injection system and determining an optimization suggestion of the column number setting;
the optimization module obtains the optimization suggestion output by the probability theory analysis module, carries out re-optimization design on the safety injection system, then carries out iterative analysis by combining the accident analysis of the determinism analysis module, and finally determines and outputs the optimization design scheme of the safety injection system.
5. The risk guidance-based nuclear power plant safety injection system simulation system according to claim 4, wherein the accidents of the nuclear power plant requiring the safety injection function, identified by the determinant analysis module, comprise design benchmark accidents and design extension accidents of the nuclear power plant, comprising reactor coolant pipeline breakage accidents, main steam pipeline breakage accidents and transient faults of failure to expect shutdown.
6. The risk guidance-based nuclear power plant safety injection system simulation system according to claim 4, wherein the deterministic analysis module performs quantitative analysis on accidents requiring the safety injection system by a deterministic analysis method, determines restrictive requirements on the safety injection flow and the boron concentration under different accident conditions, analyzes the influence of mistaken investment of the safety injection system, determines the maximum restrictive requirement on the safety injection flow, and determines the minimum cut-off set of the functional requirements of the safety injection system, including the minimum requirements on the high-pressure, medium-pressure and low-pressure safety injection flows, the maximum flow limit for the high-pressure injection and the minimum and maximum restrictive requirements on the boron concentration.
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| "基于PSA分析结果的AP1000系统设计改进建议";王成章 等;《核科学与工程》;20151231;第35卷(第4期);第723-728页 * |
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