Recognition method and device for core damage state codes
By identifying and combining the feature amounts in the core damage status file, the problems of low efficiency in the current technology of event tree judgment and excessive input amount are solved, and the automatic identification and merging of core damage status encoding is realized, which improves the nuclear power plant efficiency and accuracy of risk assessment.
Patent Information
- Application Number
- CN202411337055.1
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- Filing Date
- 2024-09-24
- Publication Date
- 2025-01-07
AI Technical Summary
In the prior art, relying on event trees to determine the inefficiency problem of core damage sequence attribute coding, and the excessive input of secondary probability safety analysis (PSA) has failed to effectively solve the problem of core damage status identification and risk assessment of nuclear power plants. Efficiency and accuracy.
By obtaining the core damage status file, determine the factors that affect the system's successful mitigation and containment failure, establish a feature quantity recognition model, identify the attribute encoding of each accident sequence, and merge it through the core damage status group model to form a core damage status Encoding, realizes automated identification and merger.
It improves the recognition efficiency of core damage status encoding, reduces the input amount of secondary PSA analysis, and supports more effective serious accident process and radioactive release risk analysis.
Smart Images
Figure CN119272189A_ABST
Abstract
Description
Technical Field
[0001] The invention relates to the field of nuclear power design, and in particular to a method and a device for identifying core damage state coding. Background Art
[0002] Nuclear power plants need to carry out probabilistic safety analysis (PSA) to evaluate the risk levels of core damage, large-scale radioactive release, and off-site radioactive consequences. As an important part of nuclear power design, PSA is crucial to the safety assessment of nuclear power plants and the balance between safety and economy. PSA of large pressurized water reactor nuclear power plants is generally divided into primary, secondary, and tertiary PSA. Among them, the secondary PSA analysis uses the core damage sequence obtained by the primary PSA as input. The primary PSA analysis often obtains a huge number (hundreds) of core damage sequences. In the secondary PSA, these core damage sequences need to be re-determined, identified, and merged to obtain the core damage status, and then conduct severe accident process and phenomenon analysis to obtain the risk of containment failure and the risk of large-scale radioactive release.
[0003] The existing patent CN114997437A discloses a method and system for calculating the core damage frequency based on the production tasks of a nuclear power plant. The method includes: obtaining the work order information of each device when performing the production tasks of the nuclear power plant within a preset period; screening out the work order information of the equipment related to the PSA risk; and calculating the core damage frequency of the production tasks of the nuclear power plant based on the screened work order information. This scheme is used to realize the automatic calculation of the core damage frequency of the nuclear power production task, but does not solve the inefficiency problem of the corresponding attribute coding of the accident sequence determined by the event tree in the prior art, and the problem of excessive input of the secondary PSA analysis.
[0004] The existing patent CN113762742A discloses a method for classifying design changes of nuclear power plants combined with probabilistic safety analysis, including: collecting design change information; preparing for full-range probabilistic safety analysis; using full-range probabilistic safety analysis to conduct qualitative analysis on design changes, and if it does not affect the probabilistic safety analysis results, using deterministic classification to determine the classification results of design changes; if it affects the probabilistic safety analysis results, using full-range probabilistic safety analysis to conduct quantitative analysis on design changes to determine the degree of influence of design changes on the probabilistic safety analysis results; judging the degree of influence of probabilistic safety analysis results according to risk judgment criteria, and obtaining the classification results of design changes. This scheme focuses on the management of design changes of nuclear power plants, and does not solve the inefficiency problem of the attribute coding corresponding to the accident sequence judged by relying on the event tree in the prior art, and the problem of excessive input of the secondary PSA analysis.
[0005] In summary, the above two patents do not solve the problem of low efficiency in the prior art of relying on event trees to judge the corresponding attribute coding of accident sequences, and the problem of excessive input volume of secondary PSA analysis. Summary of the invention
[0006] Based on the above technical problems, the present invention proposes a method and device for identifying core damage state coding, which solves the low efficiency problem of relying on event tree to judge the corresponding attribute coding of accident sequence in the prior art, and the problem of excessive input amount of secondary PSA analysis.
[0007] To achieve the above object, the present invention proposes a method for identifying core damage state coding.
[0008] A method for identifying a core damage state code, comprising:
[0009] Obtain core damage status file;
[0010] Determine N characteristic quantities based on factors affecting system mitigation success and / or factors affecting severe accident phenomena leading to containment failure;
[0011] Establish recognition models for each feature quantity;
[0012] According to the preset feature quantity recognition order, the recognition model is used to sequentially recognize the attribute codes corresponding to the attributes in the feature quantity of each accident sequence in the core damage state file;
[0013] The attribute codes are sequentially combined to form the core damage state code of each accident sequence.
[0014] Furthermore, it also includes:
[0015] Establish core damage state group model;
[0016] The core damage state group model is used to merge the core damage state codes.
[0017] Furthermore, the core damage status file is obtained, including:
[0018] Obtain the first-level PSA analysis results, which include the accident sequence ID file and the accident sequence status file;
[0019] The accident sequence status file is screened to obtain a core damage accident sequence whose accident sequence status is core damage;
[0020] The core damage accident sequence and accident sequence ID files are merged to obtain the core damage status file.
[0021] Furthermore, the N feature quantities include:
[0022] One or more of primary circuit integrity, secondary circuit integrity, containment integrity, reactor melt time, power supply status, primary circuit pressure and shutdown status.
[0023] Furthermore, a recognition model for each feature quantity is established, including:
[0024] Obtain the attributes and corresponding attribute codes contained in one or more characteristic quantities of primary circuit integrity, secondary circuit integrity, containment integrity, reactor melt time, power supply status, primary circuit pressure and shutdown status,
[0025] The attributes included in the primary loop integrity are one or more of the following: primary loop system opening, interface loss of coolant accident, steam generator heat transfer tube rupture SGTR, reactor pressure vessel RPV rupture, primary loop system intact, expected transient ATWS without emergency shutdown, large break coolant loss accident, medium break coolant loss accident and small break coolant loss accident, wherein the attribute code corresponding to the primary loop system opening is the first preset code, the attribute code corresponding to the interface loss of coolant accident is the second preset code, the attribute code corresponding to the SGTR is the third preset code, the attribute code corresponding to the RPV rupture is the fourth preset code, the attribute code corresponding to the primary loop system intact is the fifth preset code, the attribute code corresponding to the ATWS is the sixth preset code, the attribute code corresponding to the large break coolant loss accident is the seventh preset code, the attribute code corresponding to the medium break coolant loss accident is the eighth preset code, and the attribute code corresponding to the small break coolant loss accident is the ninth preset code.
[0026] The attributes included in the secondary circuit integrity are one or both of the secondary circuit system being intact and the breach. The attribute code corresponding to the secondary circuit system being intact is the tenth preset code, and the attribute code corresponding to the breach is the eleventh preset code.
[0027] The attributes of containment integrity include one or both of bypass and containment integrity. The attribute code corresponding to bypass is the twelfth preset code, and the attribute code corresponding to containment integrity is the thirteenth preset code.
[0028] The attributes included in the heap melting time are one or both of fast and slow. The attribute code corresponding to fast is the fourteenth preset code, and the attribute code corresponding to slow is the fifteenth preset code.
[0029] The attributes included in the power supply status are one or both of the plant-wide power outage accident SBO and the non-plant-wide power outage accident. The attribute code corresponding to the SBO is the sixteenth preset code, and the attribute code corresponding to the non-SBO is the seventeenth preset code.
[0030] The attributes included in the primary circuit pressure are one or both of the low-pressure melting pile and the high-pressure melting pile. The attribute code corresponding to the low-pressure melting pile is the eighteenth preset code, and the attribute code corresponding to the high-pressure melting pile is the nineteenth preset code.
[0031] The attributes included in the shutdown state are one or more of the failure of shutdown before the residual heat removal system is connected, the success of shutdown before the residual heat removal system is connected, POSD planned shutdown, POSE planned shutdown, and POSF planned shutdown. The attribute code corresponding to the failure of shutdown before the residual heat removal system is connected is the twentieth preset code, the attribute code corresponding to the success of shutdown before the residual heat removal system is connected is the twenty-first preset code, the attribute code corresponding to the POSD planned shutdown is the twenty-second preset code, the attribute code corresponding to the POSE planned shutdown is the twenty-third preset code, and the attribute code corresponding to the POSF planned shutdown is the twenty-fourth preset code;
[0032] According to the attributes contained in the characteristic quantity and the corresponding attribute codes, the corresponding primary circuit integrity identification model, secondary circuit integrity identification model, containment integrity identification model, reactor melt time identification model, power supply status identification model, primary circuit pressure identification model and shutdown status identification model are established.
[0033] To achieve the above object, the present invention proposes a device for identifying core damage status coding.
[0034] A core damage state coding identification device, comprising:
[0035] An acquisition module is used to obtain the core damage status file;
[0036] A determination module, for determining N characteristic quantities based on factors affecting system mitigation success and / or factors affecting severe accident phenomena leading to containment failure;
[0037] Establishing a module for establishing a recognition model for each feature quantity;
[0038] An identification module is used to identify the attribute codes corresponding to the attributes in the feature quantities of each accident sequence in the core damage state file in sequence by using the identification model according to a preset feature quantity identification sequence;
[0039] The combination module is used to sequentially combine the attribute codes to form the core damage state codes of each accident sequence.
[0040] Furthermore, a merging module is included, which is used to:
[0041] Establish core damage state group model;
[0042] The core damage state group model is used to merge the core damage state codes.
[0043] Furthermore, a module is obtained for:
[0044] Obtain the first-level PSA analysis results, which include the accident sequence ID file and the accident sequence status file;
[0045] The accident sequence status file is screened to obtain a core damage accident sequence whose accident sequence status is core damage;
[0046] The core damage accident sequence and accident sequence ID files are merged to obtain the core damage status file.
[0047] Furthermore, the N feature quantities include:
[0048] One or more of primary circuit integrity, secondary circuit integrity, containment integrity, reactor melt time, power supply status, primary circuit pressure and shutdown status.
[0049] Furthermore, a module is established for:
[0050] Obtain the attributes and corresponding attribute codes contained in one or more characteristic quantities of primary circuit integrity, secondary circuit integrity, containment integrity, reactor melt time, power supply status, primary circuit pressure and shutdown status,
[0051] The attributes included in the primary loop integrity are one or more of the following: primary loop system opening, interface loss of coolant accident, steam generator heat transfer tube rupture SGTR, reactor pressure vessel RPV rupture, primary loop system intact, expected transient ATWS without emergency shutdown, large break coolant loss accident, medium break coolant loss accident and small break coolant loss accident, wherein the attribute code corresponding to the primary loop system opening is the first preset code, the attribute code corresponding to the interface loss of coolant accident is the second preset code, the attribute code corresponding to the SGTR is the third preset code, the attribute code corresponding to the RPV rupture is the fourth preset code, the attribute code corresponding to the primary loop system intact is the fifth preset code, the attribute code corresponding to the ATWS is the sixth preset code, the attribute code corresponding to the large break coolant loss accident is the seventh preset code, the attribute code corresponding to the medium break coolant loss accident is the eighth preset code, and the attribute code corresponding to the small break coolant loss accident is the ninth preset code.
[0052] The attributes included in the secondary circuit integrity are one or both of the secondary circuit system being intact and the breach. The attribute code corresponding to the secondary circuit system being intact is the tenth preset code, and the attribute code corresponding to the breach is the eleventh preset code.
[0053] The attributes of containment integrity include one or both of bypass and containment integrity. The attribute code corresponding to bypass is the twelfth preset code, and the attribute code corresponding to containment integrity is the thirteenth preset code.
[0054] The attributes included in the heap melting time are one or both of fast and slow. The attribute code corresponding to fast is the fourteenth preset code, and the attribute code corresponding to slow is the fifteenth preset code.
[0055] The attributes included in the power supply status are one or both of the plant-wide power outage accident SBO and the non-plant-wide power outage accident. The attribute code corresponding to the SBO is the sixteenth preset code, and the attribute code corresponding to the non-SBO is the seventeenth preset code.
[0056] The attributes included in the primary circuit pressure are one or both of the low-pressure melting pile and the high-pressure melting pile. The attribute code corresponding to the low-pressure melting pile is the eighteenth preset code, and the attribute code corresponding to the high-pressure melting pile is the nineteenth preset code.
[0057] The attributes included in the shutdown state are one or more of the failure of shutdown before the residual heat removal system is connected, the success of shutdown before the residual heat removal system is connected, POSD planned shutdown, POSE planned shutdown, and POSF planned shutdown. The attribute code corresponding to the failure of shutdown before the residual heat removal system is connected is the twentieth preset code, the attribute code corresponding to the success of shutdown before the residual heat removal system is connected is the twenty-first preset code, the attribute code corresponding to the POSD planned shutdown is the twenty-second preset code, the attribute code corresponding to the POSE planned shutdown is the twenty-third preset code, and the attribute code corresponding to the POSF planned shutdown is the twenty-fourth preset code;
[0058] According to the attributes contained in the characteristic quantity and the corresponding attribute codes, the corresponding primary circuit integrity identification model, secondary circuit integrity identification model, containment integrity identification model, reactor melt time identification model, power supply status identification model, primary circuit pressure identification model and shutdown status identification model are established.
[0059] Based on the above technical solution, the present invention has at least the following beneficial effects:
[0060] 1. The present invention obtains the core damage status file, establishes a corresponding feature quantity recognition model according to the characteristics of the reactor type, and uses the recognition model to quickly identify the attribute codes corresponding to the attributes of each accident sequence in the feature quantity in the core damage status file, so as to form the core damage status code of each accident sequence. Compared with the method of relying on the event tree to judge the accident sequence state and the corresponding attribute code in the prior art, it is more convenient and realizes the automation of attribute coding and core damage status code recognition.
[0061] 2. After forming the core damage state codes of the accident sequence, the present invention merges the core damage state codes through the established core damage state group model to obtain the core damage states and core damage state groups corresponding to each accident sequence. This method can solve the input overload problem of the secondary PSA analysis, which is beneficial to carry out severe accident process and phenomenon analysis in the secondary PSA analysis, and obtain the risk of containment failure and the risk of large-scale radioactive release. BRIEF DESCRIPTION OF THE DRAWINGS
[0062] The accompanying drawings constituting a part of the present invention are used to provide a further understanding of the present invention. The exemplary embodiments of the present invention and their descriptions are used to explain the present invention and do not constitute an improper limitation of the present invention. In the accompanying drawings:
[0063] Figure 1 A flow chart of a method for identifying core damage state coding according to an embodiment of the present invention;
[0064] Figure 2 A flowchart of obtaining a core damage status file in one embodiment of the present invention;
[0065] Figure 3 A flow chart of a method for identifying core damage state coding according to another embodiment of the present invention;
[0066] Figure 4 The present invention is a schematic diagram of a device for identifying core damage status coding according to an embodiment of the present invention. DETAILED DESCRIPTION
[0067] It should be noted that, in the absence of conflict, the embodiments of the present invention and the features in the embodiments can be combined with each other. The present invention will be described in detail below with reference to the accompanying drawings and in combination with the embodiments.
[0068] The present invention is further described in detail below in conjunction with specific embodiments. These embodiments should not be construed as limiting the scope of protection claimed by the present invention.
[0069] Example
[0070] In order to solve the problem of low efficiency in the prior art of relying on event tree to judge the corresponding attribute coding of accident sequence and the problem of excessive input of secondary PSA analysis, the present invention proposes a method and device for identifying core damage state coding.
[0071] To achieve the above object, the present invention proposes a method for identifying core damage state coding.
[0072] like Figure 1 FIG. 4 is a flow chart of a method for identifying a core damage state code according to an embodiment of the present invention. Figure 1 As shown, the method comprises the following steps:
[0073] S1, obtain the core damage status file.
[0074] like Figure 2 As shown in the figure, obtaining the core damage status file includes the following three sub-steps:
[0075] S101, obtaining a primary PSA analysis result.
[0076] The analysis results include an accident sequence ID file and an accident sequence status file.
[0077] S102, screening the accident sequence status file to obtain a core damage accident sequence whose accident sequence status is core damage.
[0078] This embodiment takes a reactor in a nuclear power plant as an example to obtain a first-level PSA result in a probabilistic safety analysis. The accident sequence status in the accident sequence status file includes two types: OK and CD, where OK indicates that the core is intact and CD indicates that the core is damaged. This embodiment screens out the sequences with the accident sequence status of CD to form a core damage accident sequence.
[0079] S103, merging the core damage accident sequence and the accident sequence ID file to obtain a core damage status file.
[0080] The core damage accident sequence includes a sequence number and a sequence status field, and the accident sequence ID file includes a sequence code and a sequence number. The core damage accident sequence and the accident sequence ID file can be matched and merged through the sequence numbers in the two files.
[0081] S2, determining N characteristic quantities based on factors affecting the success of system mitigation and / or factors affecting severe accident phenomena leading to containment failure.
[0082] In a specific embodiment of the present invention, the factor affecting the success of mitigation of a system in a certain reactor type is mainly the decay heat level, which can be measured by the reactor melt time. Therefore, the corresponding characteristic quantity is determined to be the reactor melt time, and its corresponding attributes include fast and slow; the factors affecting the serious accident phenomenon leading to containment failure include the primary circuit pressure. If the primary circuit pressure is too high, direct containment heating (DCH) may occur, resulting in containment failure. If the primary circuit pressure is very low, there is no need to consider the failure risk. Therefore, the corresponding characteristic quantity can be determined to be the primary circuit pressure.
[0083] This embodiment determines seven characteristic quantities based on the factors that affect the success of system mitigation in the reactor and the factors that affect the failure of the containment due to severe accident phenomena: primary circuit integrity, secondary circuit integrity, containment integrity, reactor melt time, power supply status, primary circuit pressure and shutdown status. It is understandable that the characteristic quantities determined for different reactors may be different.
[0084] S3, establishing a recognition model for each feature quantity.
[0085] Furthermore, a recognition model for each feature quantity is established, including:
[0086] S301, obtaining attributes and corresponding attribute codes included in one or more characteristic quantities of primary circuit integrity, secondary circuit integrity, containment integrity, reactor melt time, power supply status, primary circuit pressure and shutdown status.
[0087] The attributes included in the primary loop integrity are one or more of the primary loop system opening, interface loss of coolant accident, steam generator heat transfer tube rupture SGTR, reactor pressure vessel RPV rupture, primary loop system intact, expected transient ATWS without emergency shutdown, large break coolant loss accident, medium break coolant loss accident and small break coolant loss accident. Among them, the attribute code corresponding to the primary loop system opening is the first preset code, the attribute code corresponding to the interface loss of coolant accident is the second preset code, the attribute code corresponding to the SGTR is the third preset code, the attribute code corresponding to the RPV rupture is the fourth preset code, the attribute code corresponding to the primary loop system intact is the fifth preset code, the attribute code corresponding to the ATWS is the sixth preset code, the attribute code corresponding to the large break coolant loss accident is the seventh preset code, the attribute code corresponding to the medium break coolant loss accident is the eighth preset code, and the attribute code corresponding to the small break coolant loss accident is the ninth preset code. Specifically, in this embodiment, the first preset code is O, the second preset code is V, the third preset code is G, the fourth preset code is R, the fifth preset code is T, the sixth preset code is A, the seventh preset code is L, the eighth preset code is M, and the ninth preset code is S.
[0088] The attributes included in the secondary loop integrity are that the secondary loop system is intact and has breaches. The attribute code corresponding to the integrity of the secondary loop system is the tenth preset code, and the attribute code corresponding to the breach is the eleventh preset code. In this embodiment, the tenth preset code is 1, and the eleventh preset code is 0.
[0089] The attributes included in the containment integrity are one or both of bypass and containment integrity. The attribute code corresponding to the bypass is the twelfth preset code, and the attribute code corresponding to the containment integrity is the thirteenth preset code. Among them, the twelfth preset code of this embodiment is B, and the thirteenth preset code is I.
[0090] The attributes included in the heap melting time are fast and slow. The attribute code corresponding to fast is the fourteenth preset code, and the attribute code corresponding to slow is the fifteenth preset code. Among them, the fourteenth preset code of this embodiment is F, and the fifteenth preset code is S.
[0091] The attributes of the power supply status include the plant-wide power outage accident SBO and the non-plant-wide power outage accident. The attribute code corresponding to SBO is the sixteenth preset code, and the attribute code corresponding to non-SBO is the seventeenth preset code. Among them, the sixteenth preset code of this embodiment is F, and the seventeenth preset code is S.
[0092] The attributes included in the primary circuit pressure are low-pressure melt pile and high-pressure melt pile. The attribute code corresponding to the low-pressure melt pile is the eighteenth preset code, and the attribute code corresponding to the high-pressure melt pile is the nineteenth preset code. Among them, the eighteenth preset code of this embodiment is L, and the nineteenth preset code is H.
[0093] The attributes included in the shutdown state are one or more of the failure of shutdown before the access of the residual heat removal system, the success of shutdown before the access of the residual heat removal system, the planned shutdown of POSD, the planned shutdown of POSE, and the planned shutdown of POSF. The attribute code corresponding to the failure of shutdown before the access of the residual heat removal system is the 20th preset code, the attribute code corresponding to the successful shutdown before the access of the residual heat removal system is the 21st preset code, the attribute code corresponding to the planned shutdown of POSD is the 22nd preset code, the attribute code corresponding to the planned shutdown of POSE is the 23rd preset code, and the attribute code corresponding to the planned shutdown of POSF is the 24th preset code. Among them, the 20th preset code of this embodiment is X, the 21st preset code is T, the 22nd preset code is D, the 23rd preset code is E, and the 24th preset code is F. It should be understood that the attribute code corresponding to the attribute of the characteristic quantity can be set according to habit or actual situation.
[0094] S302, according to the attributes contained in the feature quantity and the corresponding attribute codes, establish corresponding primary loop integrity identification model, secondary loop integrity identification model, containment integrity identification model, reactor melt time identification model, power supply status identification model, primary loop pressure identification model and shutdown status identification model.
[0095] S4, according to a preset feature quantity recognition order, using the recognition model to sequentially recognize the attribute codes corresponding to the attributes in the feature quantity of each accident sequence in the core damage status file.
[0096] The preset feature quantity recognition order in this embodiment is: primary circuit integrity, secondary circuit integrity, containment integrity, reactor melt time, power supply status, primary circuit pressure and shutdown status feature quantity recognition. The following will describe in detail the process of using the corresponding recognition model to sequentially identify the attribute coding corresponding to each attribute in the feature quantity of each accident sequence in the core damage status file.
[0097] (1) A loop integrity feature identification model is used to identify the attribute codes corresponding to the attributes in the feature of each accident sequence in the core damage status file.
[0098] The ID of the accident sequence includes several headers. For example, a certain accident sequence ID is AB_ET_LOOP-S03, wherein AB_ET_LOOP is the first header and S03 is the second header. When the accident sequence ID starts with F_ and does not contain ISLOCA in the header, the corresponding attribute is a loop integrity open, and the attribute code is O; when a header of the accident sequence ID contains ISLOCA, or a header of the accident sequence ID contains LOCA and there is another header containing R06, or a header of the accident sequence ID contains LOCA and there is another header containing R05, the corresponding attribute is interface loss of coolant accident, and the attribute code is V; when a header of the accident sequence ID contains ISGTR or SGTR, or a header of the accident sequence ID contains SLB and there is another header containing Z01, the corresponding attribute is SGTR, and the attribute code is G; when a header of the accident sequence ID contains VRLOCA, or a header of the accident sequence ID contains CP and there is another header containing S06, the corresponding attribute is RPV rupture, and the attribute code is R; when a header of the accident sequence ID contains ATWS1 or ATWS 2 or ATWS3, and other headers do not contain S04, the corresponding attribute is ATWS, and the attribute code is A; when a header of the accident sequence ID contains LLOCA, the corresponding attribute is a large loss of coolant accident, and the attribute code is L; when a header of the accident sequence ID contains MLOCA, or a header of the accident sequence ID contains ATWS and there is another header containing S05, the corresponding attribute is a medium loss of coolant accident, and the attribute code is M; when a header of the accident sequence ID contains AB_SLOCA or D_SLOCA or E_SLOCA, or a header of the accident sequence ID contains LOOP and there is another header containing S04, or a header of the accident sequence ID contains TWCC and there is another header containing S04, the corresponding attribute is a small loss of coolant accident, and the attribute code is S; when the accident sequence ID does not meet the above conditions, the attribute corresponding to the accident sequence is that the primary circuit system is intact, and the attribute code is T.
[0099] (2) Using the secondary circuit integrity identification model, the attribute codes corresponding to the attributes in the secondary circuit integrity feature quantity of each accident sequence in the core damage status file are identified.
[0100] When a header of the accident sequence ID contains ISGTR or SLB or SLLB or FLB, or a header of the accident sequence ID contains SGTR and there is another header containing V04, the corresponding attribute is a breach, and the corresponding attribute code is O; when the accident sequence ID does not meet the above conditions, the attribute corresponding to the accident sequence is that the secondary circuit system is intact, and the corresponding attribute code is I.
[0101] (3) Using the containment integrity identification model, the attribute codes corresponding to the attributes in the containment integrity feature quantity of each accident sequence in the core damage status file are identified.
[0102] When a header of the accident sequence ID contains ISGTR or ISLOCA, or a header of the accident sequence ID contains SGTR and there is another header containing V04, or a header of the accident sequence ID contains SLB and there is another header containing Z01, or a header of the accident sequence ID contains LOCA and there is another header containing R06 or R05, the attribute corresponding to the accident sequence is bypass, and the corresponding attribute code is B; when the accident sequence ID does not meet the above conditions, the attribute corresponding to the accident sequence is that the containment is intact, and the corresponding attribute code is I.
[0103] (4) Using the reactor melt time identification model, the attribute codes corresponding to the attributes in the reactor melt time feature quantity of each accident sequence in the core damage status file are identified.
[0104] When a header of the accident sequence ID contains B02 or A01 or A02 or B04 or ATWS or VRLOCA or DIL1 or DIL2 or DIL3, or a header of the accident sequence ID contains LLOCA and there is another header containing N01 or L01, or a header of the accident sequence ID contains MLOCA and there is another header containing P01 or I01, or the first bit of the accident sequence ID is C and a header contains F02, or the first bit of the accident sequence ID is C and a header contains MLOCA and N03, the attribute corresponding to the accident sequence is fast, and the corresponding attribute code is F.
[0105] When the accident sequence ID does not satisfy the above conditions, the attribute corresponding to the accident sequence is slow, and the corresponding attribute code is S.
[0106] (5) Using the power state recognition model, the attribute codes corresponding to the attributes in the power state feature quantity of each accident sequence in the core damage state file are identified.
[0107] When a header of the accident sequence ID contains LOOP and there is another header containing D06, the attribute corresponding to the accident sequence is SBO, and the corresponding attribute code is F; when the accident sequence ID does not meet the above conditions, the attribute corresponding to the accident sequence is non-SBO, and the corresponding attribute code is S.
[0108] (6) Using the primary-loop pressure identification model, the attribute codes corresponding to the attributes in the primary-loop pressure characteristic quantity of each accident sequence in the core damage status file are identified.
[0109] When the first two digits of the accident sequence ID are AB or the first digit is C, and a header contains SGTR, and there is another header containing M01 or H01; or the first two digits of the accident sequence ID are AB or the first digit is C, and a header contains SGTR, and there is another header that does not contain M01; or the first two digits of the accident sequence ID are AB or the first digit is C, and a header contains MLOCA, and there is another header that contains M01 or H01; or the first two digits of the accident sequence ID are AB or the first digit is C, and a header contains When the header contains MLOCA and there is another header that does not contain M01; or the first two digits of the accident sequence ID are coded AB or the first digit is coded C, and one of the headers does not contain SGTR or MLOCA or LLOCA or VRLOCA; or the first digit of the accident sequence ID is coded D or E, and one of the headers contains DIL; or the first digit of the accident sequence ID is coded D or E, and one of the headers does not contain DIL or CP, and there is another header that contains S04 or G01, the attribute corresponding to the accident sequence is high-pressure melt, and the corresponding attribute code is H.
[0110] When the first two digits of the accident sequence ID are AB or the first digit is C, and a header contains LLOCA or VRLOCA; or the first two digits of the accident sequence ID are AB or the first digit is C, and a header contains SGTR, and there is another header that contains M01 but not H01; or the first two digits of the accident sequence ID are AB or the first digit is C, and a header contains MLOCA, and there is another header that contains M01 but not H01 and I01; or the first digit of the accident sequence ID is D or E, and a header contains CP; or the first digit of the accident sequence ID is D or E, and a header does not contain DIL or CP, and there is another header that does not contain S04 or G01; or the first digit of the accident sequence ID is D or E, and a header does not contain DIL or CP, the attribute corresponding to the accident sequence is a low-pressure melt, and the corresponding attribute code is L.
[0111] (7) Using the shutdown state recognition model, the attribute codes corresponding to the attributes in the shutdown state feature quantity of each accident sequence in the core damage state file are identified.
[0112] When C_IE_DIL is included in a header of the accident sequence ID; or the first two digits of the accident sequence ID are AB or the first digit is C, and A01 or A02 or B01 or B02 is included in a header; or ATWS is included in a header, the corresponding attribute is that the shutdown of the residual heat removal system before access has failed, and the corresponding attribute is coded as X; when the first two digits of the accident sequence ID are AB or the first digit is C, and the header does not contain C_IE_DIL or A01 or A02 or B01 or B02 or ATWS, the corresponding attribute is that the shutdown of the residual heat removal system before access has been successful, and the corresponding attribute is coded as T; when the first digit of the accident sequence ID is D, the corresponding attribute is POSD planned shutdown, and the corresponding attribute is coded as D; when the first digit of the accident sequence ID is E, the corresponding attribute is POSE planned shutdown, and the corresponding attribute is coded as E; when the first digit of the accident sequence ID is F, the corresponding attribute is POSF planned shutdown, and the corresponding attribute is coded as F.
[0113] S5, sequentially combine the attribute codes to form the core damage state code of each accident sequence.
[0114] After the above step S4 uses the corresponding recognition model to identify the attribute codes corresponding to each attribute in the feature quantity of each accident sequence in the core damage status file in turn, each accident sequence in this embodiment will obtain corresponding seven attribute codes, and the seven attribute codes are combined to form the core damage status code of each accident sequence, such as MIIFSHT.
[0115] like Figure 3 As shown, in another embodiment of the present invention, after executing step S5, the core damage state group model is further used to merge the core damage state codes. Specifically, it includes two steps S6 and S7:
[0116] S6, establish a core damage state group model.
[0117] Based on the accident mitigation process and release consequences, a core damage state group model is established. For example, for core damage states with the characteristic quantity primary circuit pressure attribute of high-pressure melting, the characteristic quantity primary circuit integrity attribute of small and medium-sized rupture or transient, and the characteristic quantity "core melt time" attribute of fast, in the subsequent accident mitigation, the primary circuit pressure must be depressurized before the active reactor cavity is injected with water. The possibility of pressure-induced SGTR does not need to be considered, so this type of core damage state can be coded as a non-ATWS high-pressure fast core melt damage state group. According to this example idea, a core damage state group model can be established.
[0118] S7, merging the core damage state codes using the core damage state group model.
[0119] The detailed merging logic is as follows: When the first digit of the core damage status code is T or M or S, and the fourth digit is F, and the sixth digit is H, the core damage status code of the accident sequence is merged into the non-ATWS type high-pressure fast melt core damage sequence. When the first digit of the core damage status code is A, and the fourth digit is F, and the sixth digit is H, the core damage status code of the accident sequence is merged into the ATWS type high-pressure fast melt core damage sequence. When the first digit of the core damage status code is T or M or S, and the fourth digit is S, and the sixth digit is H, the core damage status code of the accident sequence is merged into the high-pressure slow melt core damage sequence. When the first digit of the core damage status code is R, the core damage status code of the accident sequence is merged into the pressure vessel rupture core damage sequence.
[0120] When the fourth digit of the core damage state code is F and the sixth digit is L, the core damage state code of the accident sequence is merged into the low-pressure fast melt core damage sequence. When the fourth digit of the core damage state code is S and the sixth digit is L, the core damage state code of the accident sequence is merged into the low-pressure fast melt slow core damage sequence. When the first digit of the core damage state code is G and the fourth digit is F, the core damage state code of the accident sequence is merged into the SGTR fast core damage sequence. When the first digit of the core damage state code is G and the fourth digit is S, the core damage state code of the accident sequence is merged into the SGTR slow core damage sequence. When the first three digits of the core damage state code are GOB, or the first digit of the core damage state code is G and the seventh digit is X, or the first digit of the core damage state code is T, the second digit is O, and the seventh digit is X, the core damage state code of the accident sequence is merged into the SGTR direct bypass containment core damage sequence. When the first three digits of the core damage state code are VIB, the core damage state code of the accident sequence is merged into the interface LOCA direct bypass containment core damage sequence.
[0121] According to the above merging logic, the core damage status codes of all power plant accident sequences are classified into ten power plant core damage status groups.
[0122] To achieve the above object, the present invention proposes a device for identifying core damage status coding.
[0123] like Figure 4 Schematic diagram of a core damage state coding identification device according to an embodiment of the present invention is shown in FIG. 4 , the device comprises: an acquisition module 41, a determination module 42, an establishment module 43, an identification module 44 and a combination module 45. The functions of each module will be described in detail below.
[0124] The acquisition module 41 is used to acquire the core damage status file.
[0125] Furthermore, the acquisition module 41 is used to:
[0126] Obtain the first-level PSA analysis results, which include the accident sequence ID file and the accident sequence status file.
[0127] The accident sequence status files are screened to obtain the core damage accident sequence whose accident sequence status is core damage.
[0128] The core damage accident sequence and accident sequence ID files are merged to obtain the core damage status file.
[0129] The determination module 42 is used to determine N characteristic quantities based on factors that affect the success of system mitigation and / or factors that affect the failure of the containment due to severe accident phenomena.
[0130] Furthermore, the N feature quantities include:
[0131] One or more of primary circuit integrity, secondary circuit integrity, containment integrity, reactor melt time, power supply status, primary circuit pressure and shutdown status.
[0132] The building module 43 is used to build a recognition model for each feature quantity.
[0133] Furthermore, a module 43 is established for:
[0134] Obtain the attributes and corresponding attribute codes contained in one or more characteristic quantities of primary circuit integrity, secondary circuit integrity, containment integrity, reactor melt time, power supply status, primary circuit pressure and shutdown status,
[0135] The attributes included in the primary loop integrity are one or more of the following: primary loop system opening, interface loss of coolant accident, steam generator heat transfer tube rupture SGTR, reactor pressure vessel RPV rupture, primary loop system intact, expected transient ATWS without emergency shutdown, large break coolant loss accident, medium break coolant loss accident and small break coolant loss accident, wherein the attribute code corresponding to the primary loop system opening is the first preset code, the attribute code corresponding to the interface loss of coolant accident is the second preset code, the attribute code corresponding to the SGTR is the third preset code, the attribute code corresponding to the RPV rupture is the fourth preset code, the attribute code corresponding to the primary loop system intact is the fifth preset code, the attribute code corresponding to the ATWS is the sixth preset code, the attribute code corresponding to the large break coolant loss accident is the seventh preset code, the attribute code corresponding to the medium break coolant loss accident is the eighth preset code, and the attribute code corresponding to the small break coolant loss accident is the ninth preset code.
[0136] The attributes included in the secondary circuit integrity are one or both of the secondary circuit system being intact and the breach. The attribute code corresponding to the secondary circuit system being intact is the tenth preset code, and the attribute code corresponding to the breach is the eleventh preset code.
[0137] The attributes of containment integrity include one or both of bypass and containment integrity. The attribute code corresponding to bypass is the twelfth preset code, and the attribute code corresponding to containment integrity is the thirteenth preset code.
[0138] The attributes included in the heap melting time are one or both of fast and slow. The attribute code corresponding to fast is the fourteenth preset code, and the attribute code corresponding to slow is the fifteenth preset code.
[0139] The attributes included in the power supply status are one or both of the plant-wide power outage accident SBO and the non-plant-wide power outage accident. The attribute code corresponding to the SBO is the sixteenth preset code, and the attribute code corresponding to the non-SBO is the seventeenth preset code.
[0140] The attributes included in the primary circuit pressure are one or both of the low-pressure melting pile and the high-pressure melting pile. The attribute code corresponding to the low-pressure melting pile is the eighteenth preset code, and the attribute code corresponding to the high-pressure melting pile is the nineteenth preset code.
[0141] The attributes included in the shutdown state are one or more of the failure of shutdown before the residual heat removal system is connected, the success of shutdown before the residual heat removal system is connected, POSD planned shutdown, POSE planned shutdown, and POSF planned shutdown. The attribute code corresponding to the failure of shutdown before the residual heat removal system is connected is the twentieth preset code, the attribute code corresponding to the success of shutdown before the residual heat removal system is connected is the twenty-first preset code, the attribute code corresponding to the POSD planned shutdown is the twenty-second preset code, the attribute code corresponding to the POSE planned shutdown is the twenty-third preset code, and the attribute code corresponding to the POSF planned shutdown is the twenty-fourth preset code;
[0142] According to the attributes contained in the characteristic quantity and the corresponding attribute codes, the corresponding primary circuit integrity identification model, secondary circuit integrity identification model, containment integrity identification model, reactor melt time identification model, power supply status identification model, primary circuit pressure identification model and shutdown status identification model are established.
[0143] The identification module 44 is used to identify the attribute codes corresponding to the attributes in the feature quantities of each accident sequence in the core damage status file in sequence by using the identification model according to a preset feature quantity identification sequence.
[0144] The combination module 45 is used to sequentially combine the attribute codes to form the core damage state codes of each accident sequence.
[0145] Furthermore, a merging module 46 is included, which is used to:
[0146] Establish a core damage state group model.
[0147] The core damage state group model is used to merge the core damage state codes.
[0148] It should be understood that a device for identifying a core damage state code is consistent with the description of a corresponding method for identifying a core damage state code, so it will not be described in detail in this embodiment.
[0149] In summary, it can be seen from the above description that the above embodiments of the present invention achieve the following technical effects:
[0150] 1. The present invention obtains the core damage status file, establishes a corresponding feature quantity recognition model according to the characteristics of the reactor type, and uses the recognition model to quickly identify the attribute codes corresponding to the attributes of each accident sequence in the feature quantity in the core damage status file, so as to form the core damage status code of each accident sequence. Compared with the method of relying on the event tree to judge the accident sequence state and the corresponding attribute code in the prior art, it is more convenient and realizes the automation of attribute coding and core damage status code recognition.
[0151] 2. After forming the core damage state codes of the accident sequence, the present invention merges the core damage state codes through the established core damage state group model to obtain the core damage states and core damage state groups corresponding to each accident sequence. This method can solve the input overload problem of the secondary PSA analysis, which is beneficial to carry out severe accident process and phenomenon analysis in the secondary PSA analysis, and obtain the risk of containment failure and the risk of large-scale radioactive release.
[0152] The above description is only a preferred embodiment of the present invention and is not intended to limit the present invention. For those skilled in the art, the present invention may have various modifications and variations. Any modification, equivalent replacement, improvement, etc. made within the spirit and principle of the present invention shall be included in the protection scope of the present invention.
[0153] It should be noted that, in this article, relational terms such as first and second, etc. are only used to distinguish one entity or operation from another entity or operation, and do not necessarily require or imply any such actual relationship or order between these entities or operations. Moreover, the terms "include", "comprise" or any other variants thereof are intended to cover non-exclusive inclusion, so that a process, method, article or device including a series of elements includes not only those elements, but also other elements not explicitly listed, or also includes elements inherent to such process, method, article or device. In the absence of further restrictions, the elements defined by the sentence "comprise a ..." do not exclude the existence of other identical elements in the process, method, article or device including the elements.
[0154] The logic and / or steps represented in the flowchart or otherwise described herein, for example, can be considered as an ordered list of executable instructions for implementing logical functions, which can be embodied in any computer-readable medium for use by an instruction execution system, apparatus or device (such as a computer-based system, a system including a processor or other system that can fetch instructions from an instruction execution system, apparatus or device and execute instructions), or used in combination with these instruction execution systems, apparatuses or devices.
[0155] It should be understood that the various parts of the present invention can be implemented by hardware, software, firmware or a combination thereof. In the above-mentioned embodiments, a plurality of steps or methods can be implemented by software or firmware stored in a memory and executed by a suitable instruction execution system. For example, if implemented by hardware, as in another embodiment, it can be implemented by any one of the following technologies known in the art or their combination: a discrete logic circuit having a logic gate circuit for implementing a logic function for a data signal, a dedicated integrated circuit having a suitable combination of logic gate circuits, a programmable gate array (PGA), a field programmable gate array (FPGA), etc.
[0156] It should be noted that, in the description of this specification, the description with reference to the terms "one embodiment", "some embodiments", "example", "specific example", or "some examples" etc. means that the specific features, structures, materials or characteristics described in conjunction with the embodiment or example are included in at least one embodiment or example of the present invention. In this specification, the schematic representations of the above terms do not necessarily refer to the same embodiment or example. Moreover, the specific features, structures, materials or characteristics described may be combined in any one or more embodiments or examples in a suitable manner. In addition, those skilled in the art may combine and combine the different embodiments or examples described in this specification and the features of the different embodiments or examples, unless they are contradictory.
Claims
1. A method for identifying core damage state coding, characterized in that: include: Obtain core damage status file; Determine N characteristic quantities based on factors affecting system mitigation success and / or factors affecting severe accident phenomena leading to containment failure; Establish recognition models for each feature quantity; According to a preset feature quantity recognition order, the attribute codes corresponding to the attributes in the feature quantity of each accident sequence in the core damage state file are sequentially recognized using the recognition model; The attribute codes are sequentially combined to form the core damage state codes of the accident sequences.
2. The method according to claim 1, characterized in that Also includes: Establish core damage state group model; The core damage state codes are merged using the core damage state group model.
3. The method according to claim 1, characterized in that: Obtain core damage status files, including: Obtaining a first-level PSA analysis result, wherein the analysis result includes an accident sequence ID file and an accident sequence status file; Screening the accident sequence status file to obtain a core damage accident sequence whose accident sequence status is core damage; The core damage accident sequence and the accident sequence ID file are merged to obtain a core damage status file.
4. The method according to claim 1, characterized in that: The N feature quantities include: One or more of primary circuit integrity, secondary circuit integrity, containment integrity, reactor melt time, power supply status, primary circuit pressure and shutdown status.
5. The method according to claim 4, characterized in that Establish recognition models for each feature quantity, including: Obtain the attributes and corresponding attribute codes contained in one or more characteristic quantities of primary circuit integrity, secondary circuit integrity, containment integrity, reactor melt time, power supply status, primary circuit pressure and shutdown status, The attributes included in the primary loop integrity are one or more of the following: primary loop system opening, interface loss of coolant accident, steam generator heat transfer tube rupture SGTR, reactor pressure vessel RPV rupture, primary loop system intact, expected transient ATWS without emergency shutdown, large break coolant loss accident, medium break coolant loss accident and small break coolant loss accident, wherein the attribute code corresponding to the primary loop system opening is the first preset code, the attribute code corresponding to the interface loss of coolant accident is the second preset code, the attribute code corresponding to the SGTR is the third preset code, the attribute code corresponding to the RPV rupture is the fourth preset code, the attribute code corresponding to the primary loop system intact is the fifth preset code, the attribute code corresponding to the ATWS is the sixth preset code, the attribute code corresponding to the large break coolant loss accident is the seventh preset code, the attribute code corresponding to the medium break coolant loss accident is the eighth preset code, and the attribute code corresponding to the small break coolant loss accident is the ninth preset code. The attributes included in the secondary loop integrity are one or both of the secondary loop system being intact and having a breach. The attribute code corresponding to the secondary loop system being intact is the tenth preset code, and the attribute code corresponding to the breach is the eleventh preset code. The attributes included in the containment integrity are one or both of bypass and containment integrity, the attribute code corresponding to the bypass is the twelfth preset code, and the attribute code corresponding to the containment integrity is the thirteenth preset code, The attributes included in the heap melting time are one or both of fast and slow. The attribute code corresponding to the fast is the fourteenth preset code, and the attribute code corresponding to the slow is the fifteenth preset code. The power supply status includes one or both of the attributes of a plant-wide power outage accident SBO and a non-plant-wide power outage accident. The attribute code corresponding to the SBO is the sixteenth preset code, and the attribute code corresponding to the non-SBO is the seventeenth preset code. The attribute included in the primary circuit pressure is one or both of a low-pressure melting pile and a high-pressure melting pile. The attribute code corresponding to the low-pressure melting pile is the eighteenth preset code, and the attribute code corresponding to the high-pressure melting pile is the nineteenth preset code. The attributes included in the shutdown state are one or more of the failure of shutdown before the residual heat removal system is connected, the success of shutdown before the residual heat removal system is connected, POSD planned shutdown, POSE planned shutdown, and POSF planned shutdown. The attribute code corresponding to the failure of shutdown before the residual heat removal system is connected is the twentieth preset code, the attribute code corresponding to the success of shutdown before the residual heat removal system is connected is the twenty-first preset code, the attribute code corresponding to the POSD planned shutdown is the twenty-second preset code, the attribute code corresponding to the POSE planned shutdown is the twenty-third preset code, and the attribute code corresponding to the POSF planned shutdown is the twenty-fourth preset code; According to the attributes contained in the characteristic quantity and the corresponding attribute codes, the corresponding primary circuit integrity identification model, secondary circuit integrity identification model, containment integrity identification model, reactor melt time identification model, power supply status identification model, primary circuit pressure identification model and shutdown status identification model are established.
6. A core damage state coding identification device, characterized in that: include: An acquisition module is used to obtain the core damage status file; A determination module, for determining N characteristic quantities based on factors affecting system mitigation success and / or factors affecting severe accident phenomena leading to containment failure; Establishing a module for establishing a recognition model for each feature quantity; An identification module, used to identify the attribute codes corresponding to the attributes in the feature quantities of each accident sequence in the core damage state file in sequence by using the identification model according to a preset feature quantity identification sequence; The combination module is used to sequentially combine the attribute codes to form the core damage state codes of each accident sequence.
7. The device according to claim 6, characterized in that It also includes a merge module for: Establish core damage state group model; The core damage state codes are merged using the core damage state group model.
8. The device according to claim 6, characterized in that The acquisition module is used to: Obtaining a first-level PSA analysis result, wherein the analysis result includes an accident sequence ID file and an accident sequence status file; Screening the accident sequence status file to obtain a core damage accident sequence whose accident sequence status is core damage; The core damage accident sequence and the accident sequence ID file are merged to obtain a core damage status file.
9. The device according to claim 6, characterized in that The N feature quantities include: One or more of primary circuit integrity, secondary circuit integrity, containment integrity, reactor melt time, power supply status, primary circuit pressure and shutdown status.
10. The device according to claim 9, characterized in that The establishment module is used to: Obtain the attributes and corresponding attribute codes contained in one or more characteristic quantities of primary circuit integrity, secondary circuit integrity, containment integrity, reactor melt time, power supply status, primary circuit pressure and shutdown status, The attributes included in the primary loop integrity are one or more of the following: primary loop system opening, interface loss of coolant accident, steam generator heat transfer tube rupture SGTR, reactor pressure vessel RPV rupture, primary loop system intact, expected transient ATWS without emergency shutdown, large break coolant loss accident, medium break coolant loss accident and small break coolant loss accident, wherein the attribute code corresponding to the primary loop system opening is the first preset code, the attribute code corresponding to the interface loss of coolant accident is the second preset code, the attribute code corresponding to the SGTR is the third preset code, the attribute code corresponding to the RPV rupture is the fourth preset code, the attribute code corresponding to the primary loop system intact is the fifth preset code, the attribute code corresponding to the ATWS is the sixth preset code, the attribute code corresponding to the large break coolant loss accident is the seventh preset code, the attribute code corresponding to the medium break coolant loss accident is the eighth preset code, and the attribute code corresponding to the small break coolant loss accident is the ninth preset code. The attributes included in the secondary loop integrity are one or both of the secondary loop system being intact and having a breach. The attribute code corresponding to the secondary loop system being intact is the tenth preset code, and the attribute code corresponding to the breach is the eleventh preset code. The attributes included in the containment integrity are one or both of bypass and containment integrity, the attribute code corresponding to the bypass is the twelfth preset code, and the attribute code corresponding to the containment integrity is the thirteenth preset code, The attributes included in the heap melting time are one or both of fast and slow. The attribute code corresponding to the fast is the fourteenth preset code, and the attribute code corresponding to the slow is the fifteenth preset code. The power supply status includes one or both of the attributes of a plant-wide power outage accident SBO and a non-plant-wide power outage accident. The attribute code corresponding to the SBO is the sixteenth preset code, and the attribute code corresponding to the non-SBO is the seventeenth preset code. The attribute included in the primary circuit pressure is one or both of a low-pressure melting pile and a high-pressure melting pile. The attribute code corresponding to the low-pressure melting pile is the eighteenth preset code, and the attribute code corresponding to the high-pressure melting pile is the nineteenth preset code. The attributes included in the shutdown state are one or more of the failure of shutdown before the residual heat removal system is connected, the success of shutdown before the residual heat removal system is connected, POSD planned shutdown, POSE planned shutdown, and POSF planned shutdown. The attribute code corresponding to the failure of shutdown before the residual heat removal system is connected is the twentieth preset code, the attribute code corresponding to the success of shutdown before the residual heat removal system is connected is the twenty-first preset code, the attribute code corresponding to the POSD planned shutdown is the twenty-second preset code, the attribute code corresponding to the POSE planned shutdown is the twenty-third preset code, and the attribute code corresponding to the POSF planned shutdown is the twenty-fourth preset code; According to the attributes contained in the characteristic quantity and the corresponding attribute codes, the corresponding primary circuit integrity identification model, secondary circuit integrity identification model, containment integrity identification model, reactor melt time identification model, power supply status identification model, primary circuit pressure identification model and shutdown status identification model are established.