CPR1000 unit ATWT periodic test optimization method, medium and equipment
By extending the ATWT T2 test cycle of CPR1000 unit and conducting reliability analysis, the problem of the existing test methods not matching DCS is solved, which improves nuclear power safety and saves costs.
Patent Information
- Application Number
- CN202411440611.8
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- Filing Date
- 2024-10-15
- Publication Date
- 2025-02-18
AI Technical Summary
The existing ATWT regular test method of CPR1000 unit does not match the digital instrumentation control system (DCS), resulting in unreasonable test cycles and methods, affecting the operational efficiency and safety of nuclear power plants.
By redetermining the test cycle of the ATWT T2 test, extending it to 18 months, and conducting reliability analysis on important instrumentation and control components, the risk increment is calculated based on the pre-constructed ATWT PSA model, and the feasibility of the test cycle is judged.
The ATWT periodic test cycle of CPR1000 unit has been optimized, which has improved nuclear power safety, while saving the operation and labor costs of nuclear power plants, and effectively optimizing the allocation of power plants' resources.
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Figure CN119476927A_ABST
Abstract
Description
Technical Field
[0001] The present invention relates to the technical field of nuclear power plant operation periodic test, and in particular to a CPR1000 unit ATWT periodic test optimization method, medium and equipment. Background Art
[0002] Most units in some nuclear power plants use digital instrumentation and control systems (DCS). The application of computer systems in nuclear power plants has replaced some of the physical equipment of the instrumentation and control systems of the power plants with computers, and some control and protection functions are implemented by computer software configuration. However, the design of the ATWT T2 supervision test in the supervision program still uses the test method of the M310 unit, and it is once every two months. The execution method and cycle of the supervision test do not match the characteristics of the DCS unit. Therefore, there is room for optimization of the test method of the CPR1000 units in these nuclear power plants. Summary of the invention
[0003] The technical problem to be solved by the present invention is to provide a CPR1000 unit ATWT periodic test optimization method, medium and equipment in view of the above-mentioned defects.
[0004] The technical solution adopted by the present invention to solve the technical problem is: a CPR1000 unit ATWT periodic test optimization method, comprising the following steps:
[0005] S1. Re-determine the test cycle of the ATWT T2 test; the re-determined test cycle is greater than the original test cycle;
[0006] S2. Conduct reliability analysis on the important instrumentation and control components required for the ATWT T2 test of the CPR1000 unit to obtain reliability parameter data before and after the test cycle is extended;
[0007] S3, based on the pre-built ATWT PSA model of the CPR1000 unit, the risk increment is calculated according to the reliability parameter data;
[0008] S4. Determine the feasibility of the re-determined test cycle according to the risk increment.
[0009] Further, in the CPR1000 unit ATWT periodic test optimization method of the present invention, the important instrumentation and control components include a logic operation module, a digital quantity input module and a digital quantity output module, and step S2 includes:
[0010] The reliability analysis of the important instrumentation and control components is performed by mathematical statistics method to obtain the reliability parameter data corresponding to each important instrumentation and control component under the original test cycle and the reliability parameter data corresponding to each important instrumentation and control component under the re-determined test cycle.
[0011] Furthermore, in the CPR1000 unit ATWT periodic test optimization method described in the present invention, the reliability parameter data includes failure probability.
[0012] Further, in the CPR1000 unit ATWT periodic test optimization method of the present invention, step S3 includes:
[0013] Modeling the important instrumentation and control components using risk-informed technology to obtain the ATWT PSA model;
[0014] The reliability parameter data before and after the test cycle is extended are used as input data of the ATWT PSA model for calculation to obtain the risk increment after the test cycle is extended.
[0015] Furthermore, in the CPR1000 unit ATWT periodic test optimization method described in the present invention, the risk increment includes the core damage probability increment and the early large-scale release probability increment.
[0016] Further, in the CPR1000 unit ATWT periodic test optimization method of the present invention, step S1 includes:
[0017] The test cycle of the ATWT T2 test is re-determined based on the current test information of the ATWT T2 test of at least one CRP1000 unit of different nuclear power plants obtained in advance.
[0018] Furthermore, in the CPR1000 unit ATWT periodic test optimization method described in the present invention, the re-determined ATWT T2 test period is 18 months.
[0019] Further, in the CPR1000 unit ATWT periodic test optimization method of the present invention, step S4 includes:
[0020] Determine whether the risk increment meets the preset criteria; if so, determine that the re-determined ATWT T2 test cycle is feasible.
[0021] In addition, the present invention also provides a computer-readable storage medium, wherein the computer-readable storage medium stores a computer program, wherein the computer program is suitable for being loaded by a processor to execute the steps of the CPR1000 unit ATWT periodic test optimization method as described above.
[0022] In addition, the present invention also provides a computer device, including a memory and a processor, wherein the memory stores a computer program, and the processor executes the steps of the above-mentioned CPR1000 unit ATWT periodic test optimization method by calling the computer program stored in the memory.
[0023] The implementation of the CPR1000 unit ATWT periodic test optimization method, medium and equipment of the present invention has the following beneficial effects: by optimizing the ATWT periodic test cycle of the CPR1000 reactor-type nuclear power plant unit, the present invention can improve nuclear power safety while greatly saving nuclear power plant operation and manpower costs, and can effectively optimize the resource allocation of the power plant. BRIEF DESCRIPTION OF THE DRAWINGS
[0024] The present invention will be further described below with reference to the accompanying drawings and embodiments, in which:
[0025] Figure 1 It is a flow chart of a CPR1000 unit ATWT periodic test optimization method provided by an embodiment of the present invention;
[0026] Figure 2 It is a schematic diagram of instrumentation and control components related to the ATWT T2 test of a CPR1000 unit provided by an embodiment of the present invention;
[0027] Figure 3 Schematic diagram of the ATWT PSA model provided by an embodiment of the present invention. DETAILED DESCRIPTION
[0028] In order to have a clearer understanding of the technical features, purposes and effects of the present invention, specific embodiments of the present invention are now described in detail with reference to the accompanying drawings.
[0029] In the following description, specific details such as specific system structures, technologies, etc. are provided for the purpose of illustration rather than limitation, so as to provide a thorough understanding of the embodiments of the present invention. However, it should be clear to those skilled in the art that the present invention may be implemented in other embodiments without these specific details. In other cases, detailed descriptions of well-known systems, devices, circuits, and methods are omitted to prevent unnecessary details from obstructing the description of the present invention.
[0030] In order to facilitate the understanding of the present invention, the present invention will be described more fully below, and the present invention can be implemented in many different forms and is not limited to the embodiments described herein. On the contrary, the purpose of providing these embodiments is to make the disclosure of the present invention more thorough and comprehensive.
[0031] It should be understood that although the terms first, second, third, etc. may be used to describe various information in the embodiments of the present invention, these information should not be limited to these terms. These terms are only used to distinguish the same type of information from each other. It is not necessarily required or implied that there is any such actual relationship or order between these entities or operations.
[0032] Unless otherwise defined, all technical and scientific terms used herein have the same meaning as those commonly understood by those skilled in the art of the present invention. The terms used in the specification of the present invention herein are only for the purpose of describing specific embodiments and are not intended to limit the present invention.
[0033] It should be noted that ATWT (Anticipated Transient Without Scram) refers to those expected transient events in nuclear power plants that will not lead to emergency shutdowns. "T2 test" generally refers to a regular detection test of the protection system for such events (expected transient events), mainly a logical test of the protection system of the nuclear power unit (CPR1000 unit) to ensure that the system can reliably perform its functions in an emergency. Other abbreviations that may be involved in the present invention include: KCS: safety-level process control cabinet system; KDS: diversity drive system; KCP: non-safety-level process control cabinet system; KIC: power plant computer information and control system; CDF (Core Damage Frequency): core damage frequency; LERF (Large Early Release Frequency): early large release frequency; PSA (Probabilistic Safety Assessment): probabilistic safety assessment.
[0034] In a preferred embodiment, reference Figure 1 The CPR1000 unit ATWT periodic test optimization method of this embodiment includes the following steps:
[0035] S1. Re-determine the test period of the ATWT T2 test. The re-determined test period is longer than the original test period. It can be understood that the re-determined test period is the extended test period, and the original test period is the test period before the extension.
[0036] Specifically, in step S1, the current test information of the ATWT T2 test of at least one CRP1000 unit of different nuclear power plants obtained in advance can be used as a reference to re-determine the test cycle of the ATWT T2 test. The current test information of the ATWT T2 test includes but is not limited to the test cycle, test method, test condition unit mode, etc. In other words, the ATWT T2 test of the CPR1000 reactor type nuclear power plant unit can be comprehensively sorted out to sort out the similarities and differences in its test principles, methods and cycles, and analyze the rationality of these similarities and differences as a reference for the optimization direction of regular tests. Of course, the extended test cycle can be determined manually, or the collected information as a reference can be entered into the system, and then the new test cycle can be determined by the preset logic of the system.
[0037] Preferably, in step S1, the re-determined ATWT T2 test period is 18 months.
[0038] S2. Reliability analysis is performed on the important instrumentation and control components required for the ATWT T2 test of the CPR1000 unit to obtain reliability parameter data before and after the test period is extended. It can be understood that the specific instrumentation and control equipment involved in the ATWT T2 test of the CPR1000 unit is analyzed, and the reliability parameter data of these instrumentation and control components are calculated through professional reliability analysis as data input for subsequent analysis. Optionally, important instrumentation and control components include but are not limited to logic operation modules, digital input modules, and digital output modules. Figure 2 The figure shows the schematic diagram of the instrumentation and control components related to the ATWT T2 test of the nuclear power unit.
[0039] Specifically, in step S2, reliability analysis is performed on important instrumentation and control components by mathematical statistics methods to obtain reliability parameter data corresponding to each important instrumentation and control component under the original test cycle and reliability parameter data corresponding to each important instrumentation and control component under the re-determined test cycle.
[0040] Optionally, the reliability parameter data includes failure rate and failure probability. Table 1 shows the reliability parameter data of the ATWT T2 test related equipment under the original test cycle. The reliability parameter data after the cycle is extended can be calculated based on the data in Table 1. The specific calculation method can refer to the prior art and will not be repeated here.
[0041] Table 1
[0042]
[0043] In Table 1, MPU is a logic operation module, DI is a digital input module, and DO is a digital output module.
[0044] S3. Based on the pre-built ATWT PSA model of the CPR1000 unit, the risk increment is calculated according to the reliability parameter data.
[0045] Specifically, step S3 includes: using risk-informed technology to model important instrumentation and control components to obtain an ATWT PSA model. Reliability parameter data before and after the test cycle is extended are used as input data of the ATWT PSA model for calculation to obtain the risk increment after the test cycle is extended.
[0046] For example, Figure 3The figure shows the schematic diagram of the ATWT PSA model for the CPR1000 reactor unit. By modeling these specific I&C components in the risk-guided calculation software (RiskSpectrum PSA), the previous calculation method that only considers ATWT failure as a whole is changed, because the failure probability of each I&C component is not the same, especially with the accumulation of operating time, the difference in failure probability may be greater. The failure probability data corresponding to each I&C component is introduced into the ATWT PSA model for calculation, thereby obtaining the risk increment.
[0047] It should be noted that the failure probability can be calculated based on the failure rate, and then the failure probability can be used as the input data of the ATWTPSA model.
[0048] Alternatively, the risk increment includes a core damage probability increment and an early large-scale release probability increment. For example, Table 2 shows the risk situation of the internal event power condition when the ATWT T2 test cycle is extended.
[0049] Table 2
[0050]
[0051] In Table 2, CDF0 is the probability of core damage before the test period is extended, CDF1 is the probability of core damage after the test period is extended, and △CDF is the increment of the probability of core damage; LERF0 is the probability of early large-scale release before the test period is extended, LERF1 is the probability of early large-scale release after the test period is extended, and △LERF is the increment of the probability of early large-scale release.
[0052] S4. Determine the feasibility of the re-determined test cycle based on the risk increment. Specifically, determine whether the risk increment meets the preset criteria. If so, the re-determined ATWT T2 test cycle is deemed feasible. It is understandable that the feasibility of extending the test cycle is determined by comparing the risk increment caused by the extension of the evaluation cycle with the allowable increment criteria in relevant laws and regulations and specifications. Such demonstration and analysis is more accurate and reliable. For example, when it is determined that the risk increment caused by the extension of the cycle meets the acceptable criteria of NNSA-0147, the ATWT T2 test cycle of the CPR1000 unit of the corresponding nuclear power plant can be optimized to once every 18 months, thereby greatly saving the operation and manpower costs of the nuclear power plant while improving safety.
[0053] It can be understood that due to the development of safety assessment technology in the nuclear industry, especially the development and application of probabilistic safety assessment (PSA) technology, risk-guided technology can demonstrate and analyze the safety-related periodic test cycle of nuclear power plants. This embodiment can improve the safety of nuclear power while greatly saving the operation and manpower costs of nuclear power plants, and can effectively optimize the resource allocation of power plants by optimizing the ATWT T2 periodic test cycle of CPR1000 reactor-type nuclear power plant units.
[0054] In a specific embodiment, regarding step S1, Table 3 shows that the current test information of ATWT tests of several CPR1000 reactor units is collected for comparison. The test cycle of the unit to be optimized can be re-determined to be 18 months based on the information in Table 3.
[0055] Table 3
[0056]
[0057] In another preferred embodiment, the CPR1000 unit ATWT periodic test optimization device of this embodiment includes:
[0058] The determination unit is used to redetermine the test cycle of the ATWT T2 test; the redetermined test cycle is greater than the original test cycle. It can be understood that the redetermined test cycle is the extended test cycle, and the original test cycle is the test cycle before the extension. Specifically, the current test information of the ATWT T2 test of at least one CRP1000 unit of different nuclear power plants obtained in advance can be used as a reference to redetermine the test cycle of the ATWT T2 test. The current test information of the ATWT T2 test includes but is not limited to the test cycle, test method, test condition unit mode, etc. In other words, the ATWT T2 test of the CPR1000 reactor type nuclear power plant unit can be comprehensively sorted out, and the similarities and differences of its test principles, methods and cycles can be sorted out, and the rationality of these similarities and differences can be analyzed as a reference for the optimization direction of regular tests. Of course, the extended test cycle can be determined manually, and the collected information as a reference can be entered into the system, and then the new test cycle is determined by the preset logic of the system. Preferably, the redetermined ATWT T2 test cycle is 18 months.
[0059] The analysis unit is used to perform reliability analysis on the important instrumentation and control components required for the ATWT T2 test of the CPR1000 unit, so as to obtain reliability parameter data before and after the test period is extended. It can be understood that the specific instrumentation and control equipment involved in the ATWT T2 test of the CPR1000 unit is analyzed, and the reliability parameter data of these instrumentation and control components are calculated through professional reliability analysis as data input for subsequent analysis. Optionally, the important instrumentation and control components include but are not limited to logic operation modules, digital input modules and digital output modules. Figure 2 The figure shows a schematic diagram of the instrumentation and control components related to the ATWT T2 test of a nuclear power unit. Specifically, the reliability analysis of the important instrumentation and control components is carried out by mathematical statistics methods to obtain the reliability parameter data corresponding to each important instrumentation and control component under the original test cycle and the reliability parameter data corresponding to each important instrumentation and control component under the re-determined test cycle.
[0060] The calculation unit is used to calculate the risk increment according to the reliability parameter data based on the pre-built ATWT PSA model of the CPR1000 unit. In other words, the important instrumentation and control components can be modeled using risk-informed technology to obtain the ATWT PSA model. The reliability parameter data before and after the test cycle is extended are used as input data of the ATWT PSA model for calculation to obtain the risk increment after the test cycle is extended.
[0061] The feasibility judgment unit is used to judge the feasibility of the re-determined test cycle according to the risk increment. Specifically, it is judged whether the risk increment meets the preset criteria. If so, it is judged that the re-determined ATWT T2 test cycle is feasible.
[0062] By optimizing the ATWT T2 periodic test cycle and verifying its feasibility, this embodiment can improve the safety of nuclear power while greatly saving the operation and manpower costs of nuclear power plants, and can effectively optimize the resource allocation of power plants.
[0063] In another preferred embodiment, the computer-readable storage medium of this embodiment stores a computer program, and the computer program is suitable for being loaded by a processor to execute the steps of the CPR1000 unit ATWT periodic test optimization method as described in the above embodiment.
[0064] In another preferred embodiment, the computer device of this embodiment includes a memory and a processor, the memory stores a computer program, and the processor executes the steps of the CPR1000 unit ATWT periodic test optimization method as described in the above embodiment by calling the computer program stored in the memory.
[0065] By extending the ATWT T2 periodic test cycle and verifying its feasibility, this embodiment can improve the safety of nuclear power while greatly saving the operation and manpower costs of nuclear power plants, and can effectively optimize the resource allocation of power plants.
[0066] The computer-readable storage medium of the present invention can be any computer-readable storage medium that can store program codes, such as a USB flash drive, a mobile hard disk, a read-only memory (ROM), a magnetic disk, or an optical disk.
[0067] The processor of the present invention is used to provide computing and control capabilities to support the operation of the entire device. It should be understood that in the embodiments of the present application, the processor may be a central processing unit (CPU), and the processor may also be other general-purpose processors, digital signal processors (DSP), application-specific integrated circuits (ASIC), field-programmable gate arrays (FPGA) or other programmable logic devices, discrete gates or transistor logic devices, discrete hardware components, etc. Among them, the general-purpose processor may be a microprocessor or the processor may also be any conventional processor, etc.
[0068] Professionals may further appreciate that the units and algorithm steps of each example described in conjunction with the embodiments disclosed herein can be implemented in electronic hardware, computer software, or a combination of the two. In order to clearly illustrate the interchangeability of hardware and software, the composition and steps of each example have been generally described in the above description according to function. Whether these functions are performed in hardware or software depends on the specific application and design constraints of the technical solution. Professionals and technicians may use different methods to implement the described functions for each specific application, but such implementation should not be considered to be beyond the scope of the present invention.
[0069] The steps of the method or algorithm described in conjunction with the embodiments disclosed herein may be implemented directly using hardware, a software module executed by a processor, or a combination of the two. The software module may be placed in a random access memory (RAM), a memory, a read-only memory (ROM), an electrically programmable ROM, an electrically erasable programmable ROM, a register, a hard disk, a removable disk, a CD-ROM, or any other form of storage medium known in the art.
[0070] It can be understood that the above embodiments only express the preferred implementation modes of the present invention, and the descriptions thereof are relatively specific and detailed, but they cannot be understood as limiting the patent scope of the present invention. It should be pointed out that, for ordinary technicians in this field, the above technical features can be freely combined without departing from the concept of the present invention, and several deformations and improvements can be made, which all belong to the protection scope of the present invention. Therefore, all equivalent changes and modifications made to the scope of the claims of the present invention should belong to the coverage of the claims of the present invention.
Claims
1. A CPR1000 unit ATWT periodic test optimization method, characterized in that: The following steps are involved: S1. Re-determine the test cycle of the ATWT T2 test; the re-determined test cycle is greater than the original test cycle; S2. Conduct reliability analysis on the important instrumentation and control components required for the ATWT T2 test of the CPR1000 unit to obtain reliability parameter data before and after the test cycle is extended; S3, based on the pre-built ATWT PSA model of the CPR1000 unit, the risk increment is calculated according to the reliability parameter data; S4. Determine the feasibility of the re-determined test cycle according to the risk increment.
2. The CPR1000 unit ATWT periodic test optimization method according to claim 1 is characterized in that: The important instrumentation and control components include a logic operation module, a digital quantity input module and a digital quantity output module. Step S2 includes: The reliability analysis of the important instrumentation and control components is performed by mathematical statistics method to obtain the reliability parameter data corresponding to each important instrumentation and control component under the original test cycle and the reliability parameter data corresponding to each important instrumentation and control component under the re-determined test cycle.
3. The CPR1000 unit ATWT periodic test optimization method according to claim 1 or 2, characterized in that: The reliability parameter data includes failure probability.
4. The CPR1000 unit ATWT periodic test optimization method according to claim 1 is characterized in that: Step S3 includes: Modeling the important instrumentation and control components using risk-informed technology to obtain the ATWT PSA model; The reliability parameter data before and after the test cycle is extended are used as input data of the ATWT PSA model for calculation to obtain the risk increment after the test cycle is extended.
5. The CPR1000 unit ATWT periodic test optimization method according to claim 4 is characterized in that: The risk increment includes the core damage probability increment and the early large-scale release probability increment.
6. The CPR1000 unit ATWT periodic test optimization method according to claim 1 is characterized in that: Step S1 includes: The test cycle of the ATWT T2 test is re-determined based on the current test information of the ATWT T2 test of at least one CRP1000 unit of different nuclear power plants obtained in advance.
7. The CPR1000 unit ATWT periodic test optimization method according to claim 1 or 6, characterized in that: The re-determined ATWT T2 trial period is 18 months.
8. The CPR1000 unit ATWT periodic test optimization method according to claim 1 is characterized in that: Step S4 includes: Determine whether the risk increment meets the preset criteria; if so, determine that the re-determined ATWT T2 test cycle is feasible.
9. A computer-readable storage medium, characterized in that: The computer-readable storage medium stores a computer program, and the computer program is suitable for being loaded by a processor to execute the steps of the CPR1000 unit ATWT periodic test optimization method as described in any one of claims 1 to 8.
10. A computer device, characterized in that: It comprises a memory and a processor, wherein the memory stores a computer program, and the processor executes the steps of the CPR1000 unit ATWT periodic test optimization method as described in any one of claims 1 to 8 by calling the computer program stored in the memory.