System and method for automating accident analysis at nuclear power plant

Abstract

The present invention provides a system and method for automating accident analysis for a nuclear power plant. The method for automating accident analysis for a nuclear power plant includes the steps of: loading primary input information including event tree information and user input information related to accident scenario information for accident analysis in a primary input information generation module; generating accident scenario information for the nuclear power plant based on the primary input information in an accident scenario information generation module; generating secondary input information for accident analysis based on the accident scenario information in a secondary input information generation module; and performing an accident analysis on the nuclear power plant based on the secondary input information in an accident analysis execution module to generate accident analysis information.

Description

[Technical field]

[0001] The present invention relates to an accident analysis automation system and an automation method for a nuclear power plant. [Background technology]

[0002] Nuclear power plant accident analysis is an essential element in the process of nuclear power plant design, design modification, and regulatory licensing. Until now, accident analysis at nuclear power plants has been performed by engineering experts in accident analysis, but there are inefficient elements that require human intervention in the accident analysis process. Furthermore, with the improvement of computer computing power and the development of artificial intelligence and big data technology, there is a need to automate the entire process of accident analysis to maximize development and engineering efficiency.

[0003] In the case of the technology using the PSA event tree, the purpose is limited to evaluating the reliability of the success criteria of the system in the probabilistic safety assessment and providing an accurate basis for the core damage frequency analysis by analyzing the accident history selected for the main systems in the nuclear power plant using the event tree data with the thermal hydraulic analysis (MAAP4) code. In other words, the accident scenario to be analyzed is limited to the core damage accident scenario, and the general automation algorithm for the accident analysis is not specifically explained, so there is a limit to achieving the purpose of automating the accident analysis. For example, the main invention content is limited to the method of selecting a severe accident scenario using the PSA event tree, and it is not possible to consider scenarios other than the selected scenario. Therefore, there is a limit to achieving the general automation of the accident analysis. Summary of the Invention [Problem to be solved by the invention]

[0004] The problem to be solved by the present invention is to automate the entire process for all accident scenario information that can occur in a nuclear power plant based on PSA information without the intervention of an analyst.

[0005] This will also result in significant savings in the engineering costs involved in accident analysis required for the design and licensing of nuclear power plants, PSA maintenance, etc.

[0006] In addition, by lowering the barrier to entry into the field of accident analysis, which requires a high level of engineering knowledge, the aim is to improve the understanding of nuclear power plant accidents among operators, accident response personnel, and other nuclear power plant workers, strengthen their accident response capabilities, and contribute to improving the safety of nuclear power plants.

[0007] In addition, since it is possible to obtain a large amount of data on the behavior of nuclear power plants and related overall accident scenarios in a short period of time, it will facilitate use in the field of artificial intelligence for nuclear power plant training and accident response.

[0008] The object of the present invention is not limited to the above-mentioned objects, and other objects not mentioned herein will be clearly understood by those skilled in the art from the following description. [Means for solving the problem]

[0009] To achieve the above object, a method for automating accident analysis of a nuclear power plant according to one aspect of the present invention includes a step of loading primary input information including event tree information and user input information related to accident scenario information for accident analysis in a primary input information generation module; a step of generating accident scenario information of the nuclear power plant based on the primary input information in an accident scenario information generation module; a step of generating secondary input information for accident analysis based on the accident scenario information in a secondary input information generation module; and a step of performing an accident analysis on the nuclear power plant based on the secondary input information in an accident analysis execution module to generate accident analysis information.

[0010] The method further includes generating, in a result report generating module, result report information based on the accident analysis information of the nuclear power plant.

[0011] The accident scenario information includes at least thousands to hundreds of thousands of accident scenarios classified by type.

[0012] The accident scenario information generation module also includes an element equipment failure information generation unit that generates first element equipment failure information due to the occurrence of a first element equipment failure among the element equipment of the nuclear power plant based on the first input information, and second element equipment failure information due to a second element equipment failure and nth element equipment failure information due to an nth element equipment failure among the element equipment of the nuclear power plant based on the first input information.

[0013] The component equipment includes at least one of pumps, valves, piping, air conditioning equipment, and electrical equipment of the nuclear power plant.

[0014] In addition, the accident scenario information generation module further includes a safety system failure information generation unit that generates safety system failure information regarding whether or not there is a failure in the operation of the safety system of the nuclear power plant corresponding to the component equipment based on the component equipment failure information.

[0015] In addition, the safety system includes a first safety system including the first element equipment and a second safety system including the second element equipment, and the safety system failure information includes first safety system failure information regarding the first safety system and second safety system failure information regarding the second safety system.

[0016] In addition, the secondary input information generation module generates accident analysis input information based on the safety system failure information, and the secondary input information is generated based on the accident analysis input information.

[0017] In addition, the step of generating the accident scenario information further includes a step 1-3 of loading nth accident scenario information, which is the nth accident scenario information among the accident scenario information; a step 1-4 of selecting nth historical information among historical information based on the nth accident scenario information; a step 1-5 of acquiring nth safety system failure information among the safety system failure information corresponding to the selected first historical information; a step 1-6 of determining whether the nth historical information episode is the final episode corresponding to the nth safety system failure information; and a step 1-7 of incrementing the nth historical information episode and proceeding to the step 1-5 if it is determined that the nth historical information episode is not the final episode in the step 1-6.

[0018] The method also includes a step 1-9 of determining whether the nth accident scenario information is the final one; and a step 1-10 of generating the accident scenario information if the nth accident scenario information is the final one.

[0019] The method further includes step 1-9, in which, if it is determined in step 1-6 that the number of the nth history information is the final number, the number of the nth accident scenario information corresponding to the nth history information is incremented.

[0020] The method further includes step 1-7 of, if the nth history information number in step 1-6 is not the final number, proceeding to step 1-5 based on the incremented nth history information number.

[0021] Also, if it is determined in step 1-9 that the round of the nth accident scenario information is not the final round, the process proceeds to step 1-3.

[0022] The method further includes step 1-1 in which analysis information of the history information is generated by analyzing the event tree information, and step 1-2 in which the analysis information obtained by analyzing the event tree information is stored in a DB, and in step 1-5, the nth safety system failure information is provided from the DB.

[0023] The step of generating the second input information includes a step 2-1 of loading the scenario information; a step 2-3 of loading n-th accident scenario information, which is the n-th accident scenario information among the accident scenario information; a step 2-4 of selecting n-th historical information among the historical information based on the n-th accident scenario information; a step 2-5 of acquiring and loading n-th computer code input information corresponding to the selected n-th historical information; a step 2-6 of determining whether the n-th historical information in the step 2-4 is the last one; The method includes a step 2-8 of generating user input variable reflection information based on the user input information and the nth computer code input information if it is determined that the round is the final round; a step 2-9 of generating variable reflection nth computer code input statement information, which is a computer code input statement based on the nth accident scenario information, based on the user input variable reflection information; a step 2-10 of determining whether the round of the nth accident scenario information in the step 2-9 is the final round; and a step 2-12 of generating the second input information including the nth computer code input statement information if the round is the final round.

[0024] The method further includes step 2-11 of incrementing the number of the nth accident scenario information and proceeding to step 2-3 if the number of the nth accident scenario information is not the final number in step 2-10.

[0025] To achieve the above object, an automated system for accident analysis of a nuclear power plant according to another aspect of the present invention includes a primary input information generation module that generates primary input information for accident analysis; an accident scenario information generation module that generates accident scenario information of the nuclear power plant based on the primary input information; a secondary input information generation module that generates secondary input information for accident analysis based on the accident scenario information; and an accident analysis execution module that performs accident analysis on the nuclear power plant based on the secondary input information and generates accident analysis information. Effect of the Invention

[0026] The present invention as described above has one or more of the following advantages.

[0027] According to the present invention, the entire process can be automated without the intervention of an analyst for all accident scenario information that can occur in a nuclear power plant based on PSA information.

[0028] This will also enable significant savings in engineering costs for accident analysis required for the design and licensing of nuclear power plants, PSA maintenance, etc.

[0029] In addition, by lowering the barrier to entry into the field of accident analysis, which requires a high level of engineering knowledge, it will be possible to improve the understanding of nuclear power plant accidents among operators, accident response personnel, and other nuclear power plant workers, strengthen their accident response capabilities, and contribute to improving the safety of nuclear power plants.

[0030] In addition, it is possible to obtain a large amount of data on the behavior of nuclear power plants and related overall accident scenarios in a short period of time, which will facilitate its use in the field of artificial intelligence for nuclear power plant training and accident response. [Brief description of the drawings]

[0031] [Figure 1] 1 is a block diagram showing an automated system for accident analysis of a nuclear power plant according to an embodiment of the present invention. [Diagram 2] FIG. 2 is a block diagram showing the configuration according to FIG. 1. [Diagram 3] FIG. 3 is a block diagram showing the configuration of FIG. 2 in detail. [Figure 4] FIG. 3 is a block diagram showing the configuration of FIG. 2 in more detail. [Diagram 5] 2 is a flowchart sequentially illustrating a method for automating accident analysis in a nuclear power plant according to an embodiment of the present invention. [Figure 6] 6 is a flowchart sequentially illustrating some steps according to FIG. 5. BEST MODE FOR CARRYING OUT THEINVENTION

[0032] The present invention relates to a method for automating accident analysis of a nuclear power plant, the method including: a step of loading primary input information including event tree information and user input information relating to accident scenario information for accident analysis in a primary input information generating module; a step of generating accident scenario information of the nuclear power plant based on the primary input information in an accident scenario information generating module; a step of generating secondary input information for accident analysis based on the accident scenario information in a secondary input information generating module; and a step of performing an accident analysis on the nuclear power plant based on the secondary input information in an accident analysis execution module to generate accident analysis information. DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS

[0033] Hereinafter, preferred embodiments of the present invention will be described in detail with reference to the accompanying drawings. Advantages and features of the present invention, as well as methods for achieving the same, will become apparent from the following detailed embodiments in conjunction with the accompanying drawings. However, the present invention is not limited to the embodiments disclosed below, and may be realized in various different forms. The present embodiments are provided merely to complete the disclosure of the present invention and to fully inform those skilled in the art of the present invention of the scope of the invention, and the present invention is defined only by the scope of the claims. The same reference symbols refer to the same elements throughout the specification.

[0034] 1 and 2, a nuclear power plant accident analysis automation system 100 (hereinafter, referred to as "system 100") according to an embodiment of the present invention includes a first input information generation module 110, an accident scenario information generation module 120, a second input information generation module 130, an accident analysis execution module 140, and a result report generation module 150. The second input information generation module 130 includes an element equipment failure information generation unit 121 and a safety system failure information generation unit 122 (see FIG. 3).

[0035] 3, the first input information generating module 110 of the system 100 generates first input information for accident analysis. The accident scenario information generating module 120 of the system 100 generates accident scenario information of a nuclear power plant based on the first input information.

[0036] A secondary input information generating module 130 of the system 100 generates secondary input information for accident analysis based on the accident scenario information. An accident analysis executing module 140 of the system 100 performs an accident analysis on the nuclear power plant based on the secondary input information to generate accident analysis information.

[0037] Furthermore, the result report generation module 150 of the system 100 generates result report information by accident analysis of the nuclear power plant based on the accident analysis information. The accident scenario information includes at least thousands to hundreds of thousands of accident scenarios by type.

[0038] The accident scenario information generation module 120 generates first element equipment failure information, second element equipment failure information, and n-th element equipment failure information based on the first input information. The first element equipment failure information is related to the occurrence of a first element equipment failure among element equipment of the nuclear power plant based on the first input information.

[0039] The second component equipment failure information is related to a second component equipment failure among the component equipment of the nuclear power plant based on the first input information. The component equipment includes at least one of pumps, valves, piping, air conditioning equipment, electrical equipment, etc. of the nuclear power plant.

[0040] The safety system failure information generating unit 122 of the accident scenario information generating module 120 generates safety system failure information regarding the presence or absence of a failure in the operation of the safety system of the nuclear power plant corresponding to the component equipment based on the component equipment failure information.

[0041] The safety systems include a first safety system including the first element equipment, a second safety system including the second element equipment, and an nth safety system including an nth element equipment. The safety system failure information includes first safety system failure information regarding the first safety system, second safety system failure information regarding the second safety system, and nth safety system failure information regarding the nth safety system.

[0042] Furthermore, the secondary input information generating module 130 generates accident analysis input information based on the safety system failure information, where the secondary input information is generated based on the accident analysis input information.

[0043] Referring to FIG. 4, in a method S100 for automating accident analysis of a nuclear power plant according to an embodiment of the present invention, first input information including event tree information and user input information related to accident scenario information for accident analysis is loaded in a first input information generation module 110.

[0044] Next, accident scenario information of the nuclear power plant is generated based on the first input information in an accident scenario information generation module 120. Secondary input information generation module 130 generates secondary input information for accident analysis based on the accident scenario information.

[0045] An accident analysis execution module 140 performs an accident analysis on the nuclear power plant based on the second input information to generate accident analysis information. A result report generation module 150 generates result report information on the accident analysis of the nuclear power plant based on the accident analysis information.

[0046] Referring to FIG. 5, in the step of generating the accident scenario information (S120), in step 1-1 (S1201), historical information including an initial event, first element equipment failure information, second element equipment failure information, and max element equipment failure information representing each accident scenario is generated by analyzing event tree information, and it is determined which safety system failure information each element equipment failure information belongs to.

[0047] Furthermore, analysis information of the history information is generated by the analysis. In step 1-2 (S1203), the analysis information obtained by analyzing the event tree information is stored in a DB. In step 1-3 (S1205), n-th accident scenario information, which is the n-th accident scenario information among the accident scenario information, is loaded.

[0048] In step 1-4 (S1207), the nth history information based on the nth accident scenario information is selected. The selection is performed from the first 1st round to the maximum maxth round.

[0049] The nth history information includes information on an initial event that occurred in the nuclear power plant and element equipment #1 through element equipment #max in which failures occurred after the initial event. When element equipment #1 fails, element equipment #2 responds to the failure of element equipment #1. When element equipment #2 fails, element equipment #3 operates in a manner that responds to the failure of element equipment #2.

[0050] Furthermore, in relation to j shown in the figure, for example, j=1 refers to an initial event that occurred at the nuclear power plant, j=2 refers to component equipment #1 in which the failure occurred after the initial event, j=3 refers to another component equipment #2 in which the failure occurred after the initial event, etc.

[0051] That is, j=1 to j=n indicate the initial event and the subsequent failures of element equipment #1 to #max in sequence. Based on this, element equipment failure information regarding the failure of element equipment is generated.

[0052] The nth safety system failure information is acquired corresponding to the nth history information or the element equipment failure information selected in step 1-5 (S1209). The nth safety system failure information is related to multiple safety systems including the element equipment, and is related to a safety system including a failed element equipment.

[0053] That is, it includes 1st safety system failure information regarding the 1st safety system to maxth safety system failure information regarding the maxth safety system. Here, the nth accident scenario information is processed to include at least a portion of the name information of the failed safety system including the failed element equipment. In the 1-5th step (S1209), the nth safety system failure information is provided from the DB.

[0054] In step 1-6 (S1211), it is determined whether the number of the nth history information included in the nth accident scenario information has reached the final number. In step 1-7 (S1213), if it is determined in step 1-6 (S1211) that the number of the nth history information is not the final number, the number of the nth history information is incremented and the process proceeds to step 1-5 (S1209).

[0055] Furthermore, the number of the nth accident scenario information is incremented in step 1-8 (S1215). It is determined in step 1-9 (S1217) whether the number of the nth accident scenario information is the final number.

[0056] In step 1-9 (S1217), if it is determined in step 1-6 (S1211) that the number of the nth history information is the final number, the number of the nth accident scenario information corresponding to the nth history information is incremented.

[0057] Here, the addition means that such addition is performed sequentially up to a preset maximum number of times, from the nth round to the n+1th round, n+2th round, and so on, to proceed to the next round.

[0058] If the number of times is the final number in step 1-10 (S1219), the accident scenario information is generated. If the number of times of the nth accident scenario information is determined not to be the final number in step 1-9 (S1217), the process proceeds to step 1-3 (S1205).

[0059] Referring to FIG. 6, in generating the second input information (S130), in step 2-1 (S1301), scenario information for the accident analysis that has gone through step 1-1 (S1201) to step 1-10 (S1219) is loaded.

[0060] In step 2-2 (S1303), the nth computer code input information is stored in a pool form so that the nth computer code input information can be provided in step 2-5 (S1309) described below. In step 2-3 (S1305), the nth accident scenario information, which is the nth accident scenario information among the accident scenario information, is loaded.

[0061] In step 2-4 (S1307), the nth historical information is selected from the historical information based on the nth accident scenario information. In step 2-5 (S1309), the nth computer code input information corresponding to the selected nth historical information is obtained and loaded. In step 2-6 (S1311), it is determined whether the nth historical information in step 2-5 (S1309) is the last one.

[0062] Further, in step 2-7 (S1313), if it is determined in step 2-6 (S1311) that the number of the nth history information is not the final number, the number of the nth history information is incremented and the process proceeds to step 2-5 (S1309).

[0063] In step 2-8 (S1313), if it is determined in step 2-6 (S1311) that the nth history information is the final one, user input variable reflection information is generated based on the user input information and the nth computer code input information.

[0064] Here, the user input variables reflected in the user input variable reflection information include at least one of information on numerical analysis related variables for objects in the nuclear power plant, a method for storing result data, a safety equipment operation system, a safety equipment operation time, an operator action time, etc.

[0065] In step 2-9 (S1317), variable reflection n-th computer code input statement information, which is a computer code input statement based on the n-th accident scenario information, is generated based on the user input variable reflection information.

[0066] Further, in step 2-10 (S1319), it is determined whether the nth accident scenario information in step 2-9 (S1317) is the final one. If the nth accident scenario information is the final one in step 2-12 (S1323), the second input information including the nth computer code input statement information is generated.

[0067] In step 2-11 (S1321), if the number of the nth accident scenario information is not the final number in step 2-10 (S1319), the number of the nth accident scenario information is incremented and the process proceeds to step 2-3 (S1305).

[0068] Although the embodiment of the present invention has been described above with reference to the accompanying drawings, those skilled in the art will understand that the present invention can be embodied in other specific forms without changing the technical idea or essential features of the present invention. Therefore, it should be understood that the above embodiment is illustrative in all respects and is not limiting.

Claims

1. In the method for automating accident analysis at a nuclear power plant, A step of loading first input information including event tree information and user input information related to accident scenario information for accident analysis into a first input information generation module; generating accident scenario information of the nuclear power plant based on the first input information in an accident scenario information generating module; generating second input information for accident analysis based on the accident scenario information in a second input information generating module; and a step of performing an accident analysis on the nuclear power plant based on the second input information in an accident analysis execution module to generate accident analysis information.

2. The method of claim 1 , further comprising: generating, in a result report generating module, result report information based on the accident analysis information, the accident analysis result of the nuclear power plant.

3. 2. The method for automating accident analysis in a nuclear power plant according to claim 1, wherein the accident scenario information includes at least thousands to hundreds of thousands of accident scenarios by type.

4. The accident scenario information generation module includes: First element equipment failure information due to the occurrence of a first element equipment failure among the element equipment of the nuclear power plant based on the first input information; 2. The method for automating accident analysis of a nuclear power plant according to claim 1, further comprising an element equipment failure information generation unit that generates second element equipment failure information due to a second element equipment failure among the element equipment of the nuclear power plant based on the first input information.

5. 5. The method for automating accident analysis in a nuclear power plant according to claim 4, wherein the elemental equipment includes at least one of pumps, valves, piping, air conditioning equipment, and electrical equipment in the nuclear power plant.

6. The accident scenario information generation module includes:

6. The method for automating accident analysis of a nuclear power plant according to claim 5, further comprising a safety system failure information generation unit that generates safety system failure information regarding the presence or absence of an operation failure of a safety system of the nuclear power plant corresponding to the component equipment based on the component equipment failure information.

7. The safety system includes: A first safety system including the first element equipment and a second safety system including the second element equipment, The safety system failure information, first safety system failure information relating to the first safety system; The method for automating accident analysis in a nuclear power plant according to claim 6 , further comprising second safety system failure information relating to the second safety system.

8. The second input information generation module includes:

7. The method for automating accident analysis in a nuclear power plant according to claim 6, further comprising generating accident analysis input information based on the safety system failure information, and generating the secondary input information based on the accident analysis input information.

9. The step of generating the accident scenario information includes: A first-1 step in which history information including an initial event, a first element equipment failure information, a second element equipment failure information, and a max element equipment failure information, which represent each accident scenario, is generated by analyzing the event tree information, and it is determined to which safety system failure information each element equipment failure information belongs; Step 1-3: loading n-th accident scenario information, which is the n-th accident scenario information among the accident scenario information; A first to fourth step of selecting an n-th piece of history information from the history information based on the n-th accident scenario information; A 1-5th step of acquiring n-th safety system failure information among the safety system failure information corresponding to the selected first history information; Step 1-6, in which it is determined whether the nth history information episode is the final episode in response to the nth safety system failure information; Step 1-7, in which if it is determined in step 1-6 that the number of the nth history information is not the final number, the number of the nth history information is incremented and the process proceeds to step 1-5; and 6. The method for automating accident analysis of a nuclear power plant according to claim 5, further comprising steps 1-10 of generating the accident scenario information if the round is a final round.

10. 10. The method for automating accident analysis of a nuclear power plant according to claim 9, further comprising: step 1-9, in which, when it is determined in step 1-6 that the number of the nth history information is the final number, an number of the nth accident scenario information corresponding to the nth history information is incremented.

11. 10. The method for automating accident analysis of a nuclear power plant according to claim 9, further comprising: step 1-7 of, when the nth history information number in step 1-6 is not the final number, proceeding to step 1-5 based on the nth history information number that has been added.

12. 11. The method for automating accident analysis of a nuclear power plant according to claim 10, further comprising the step of proceeding to step 1-3 if it is determined in step 1-9 that the round of the nth accident scenario information is not the final round.

13. a 1-1 step of generating analysis information of the history information by analyzing the event tree information; The method further includes a first-second step of storing the analysis information obtained by analyzing the event tree information in a DB, 10. The method for automating accident analysis in a nuclear power plant according to claim 9, wherein in the first to fifth steps, the nth safety system failure information is provided from the DB.

14. The step of generating the second input information includes: Step 2-1: loading the scenario information; A second-third step loads n-th accident scenario information, which is the n-th accident scenario information among the accident scenario information; A second-fourth step of selecting an n-th piece of history information from among the history information based on the n-th accident scenario information; Step 2-5: acquiring and loading n-th computer code input information corresponding to the selected n-th history information; A 2-6 step in which it is determined whether the nth history information in the 2-4 step is the final one; A 2-8 step in which user input variable reflection information is generated based on the user input information and the nth computer code input information when it is determined that the nth history information is the final history information in the 2-6 step; A 2-9th step of generating variable-reflecting n-th computer code input statement information, which is a computer code input statement based on the n-th accident scenario information, based on the user-input variable-reflecting information; A step 2-10 in which it is determined whether the nth accident scenario information in the step 2-9 is the final one; and 2. The method of claim 1, further comprising: generating the second input information including the nth computer code input statement information when the round is a final round.

15. In the second to tenth stages, 15. The method for automating accident analysis of a nuclear power plant according to claim 14, further comprising: step 2-11, when the number of the nth accident scenario information is not a final number, incrementing the number of the nth accident scenario information and proceeding to step 2-3.

16. In the accident analysis automation system for nuclear power plants, a first input information generation module that generates first input information for accident analysis; an accident scenario information generating module for generating accident scenario information of the nuclear power plant based on the first input information; a secondary input information generating module for generating secondary input information for accident analysis based on the accident scenario information; and an accident analysis execution module that performs an accident analysis on the nuclear power plant based on the secondary input information and generates accident analysis information;

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