CN113947282A - Safety evaluation independent verification method and platform for passive characteristic of third-generation nuclear power station - Google Patents
Safety evaluation independent verification method and platform for passive characteristic of third-generation nuclear power station Download PDFInfo
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Abstract
The application provides a safety evaluation independent verification method and a platform for passive characteristics of a third-generation nuclear power station, wherein the method comprises the following steps: establishing a software system suitable for passive characteristics through verification of nuclear power station operation data and test data; establishing a software system for verifying the passive characteristic and a database of the model; wherein, the database comprises relevant data of single experiment and whole experiment for verifying heap type or similar heap type; independently verifying key accidents according to the selected passive characteristic design and combining with the design data information of the nuclear power station to obtain the identification and sequencing of key phenomena; and performing calculation verification of passive characteristic superposition uncertainty analysis, and optimizing and perfecting a phenomenon identification model according to accident analysis comparison or/and uncertainty analysis results. The invention confirms the reasonable design and effectiveness of the national and first passive safety systems and confirms and perfects the critical design accident PIRT through verification and analysis, and is beneficial to the national and first passive safety systems to pass the relevant independent verification requirements and safety evaluation.
Description
Technical Field
The invention relates to the technical field of nuclear energy-safety evaluation, in particular to a safety evaluation independent verification method and platform for passive characteristics of a third-generation nuclear power station.
Background
According to the requirements of HAF102 'design safety provisions of nuclear power plants' section 3.6: before submitting to national nuclear safety supervision departments, owners must ensure that individuals or groups which do not participate in related designs perform independent verification on safety evaluation, and the HAD102/17, the nuclear power plant safety evaluation and verification, of the nuclear safety guide, provides supplementary descriptions on safety evaluation, safety analysis and independent verification. In the guideline, safety evaluation is a systematic process that runs through the entire design process to ensure that the nuclear power plant design meets all relevant safety requirements. The security assessment includes, but is not limited to, a formal security analysis. Independent verification should be done under the responsibility of the operating unit by a group of professionals who should be as independent as possible from the designer of the nuclear power plant and the personnel performing the safety evaluation. These professionals may be considered independent if they are not involved in any part of the design and safety evaluation. This independent verification is in addition to the quality assurance review performed inside the design unit. The safety evaluation is a comprehensive research work performed by a design unit in the whole design process to meet all relevant safety requirements, and the independent verification is a work completed by an operation unit or completed under the name of the operation unit, and can be only related to the design submitted by a national nuclear safety supervision department. Due to the complexity of the design and safety evaluation issues involved with independent verification, independent verification is typically performed in part during the design process, not just after the nuclear power plant design is complete. The operator has full responsibility for the independent verification even if part of the work of the independent verification is entrusted to some independent authorities.
Therefore, the independent verification is organized by the operating units, and the safety evaluation performed by the design units is examined by a group of professionals who are familiar with the design of the nuclear power plant and are familiar with the safety analysis and safety evaluation work, so as to confirm whether the safety evaluation meets the applicable safety requirements.
But the independent verification work does not have much experience at home at present, and a public and reasonable system is lacked to guide the development of related work, so that the rationality and the effectiveness of verification are ensured, the design work is further promoted, and the approval of the inspection management part door is facilitated.
Disclosure of Invention
The present invention is directed to solving, at least to some extent, one of the technical problems in the related art.
Therefore, the first purpose of the invention is to provide a safety evaluation independent verification method for the passive characteristic of the third-generation nuclear power station, and a more reasonable safety evaluation independent verification system is provided for the passive characteristic of the third-generation nuclear power station.
The second purpose of the invention is to provide a safety evaluation independent verification platform for passive characteristics of the third-generation nuclear power station.
In order to achieve the above object, an embodiment of a first aspect of the present invention provides an independent verification method for safety evaluation of passive characteristics of a third-generation nuclear power plant, including:
establishing a software system suitable for the passive characteristic by verifying the operation data and the test data of the nuclear power station and combining an autonomous development/introduction/purchase program;
establishing a database of a software system and a model for verifying the passive characteristic; wherein the database of the software system for verifying the passive characteristic comprises relevant data of single experiments and whole experiments for verifying heap type or similar heap type;
independently verifying key accidents according to the selected passive characteristic design and combining with the design data information of the nuclear power station to obtain the identification and sequencing of key phenomena; the key phenomenon identification sequences are used for selecting the single experiment and the whole experiment design for software verification and uncertainty parameters;
and carrying out calculation verification of passive characteristic superposition uncertainty analysis based on the related data, and optimizing and perfecting a phenomenon identification model according to accident analysis comparison or/and uncertainty analysis results.
In addition, the safety evaluation independent verification method for passive characteristics of the third-generation nuclear power plant according to the above embodiment of the present invention may further have the following additional technical features:
further, in an embodiment of the present invention, the software system suitable for the passive characteristic is based on an analysis program approved by an international/domestic safety evaluation organization, and needs to pass verification of the nuclear power plant operation data and test data, especially verification of the passive characteristic.
Further, in an embodiment of the present invention, the nuclear power plant operation data and test data include one or more of passive test data for a similar reactor type, benchmark test data issued by an international nuclear power agency, example questions, and operation/test data of a nuclear power plant of a similar reactor type.
Further, in one embodiment of the present invention, the analysis program approved by the international/national security evaluation agency includes: the core physical design checking program, the system program of the optimal estimation, other thermal hydraulic system analysis programs and the containment response analysis program.
Further, in an embodiment of the present invention, the optimizing and perfecting the phenomenon recognition model according to the comparison of the results calculated by different accident analysis procedures or/and the uncertainty analysis results includes: and establishing an accident analysis reference model according to the nuclear power station design data information, and performing node division confirmation and uncertainty analysis steps and analysis comparison of different program results based on the accident analysis reference model.
Further, in an embodiment of the present invention, the comparing the results or/and the uncertainty analysis results according to different accident analysis procedures to optimize and perfect the phenomenon recognition model further includes:
and selecting the uncertainty parameters based on the accident analysis reference model to carry out uncertainty analysis.
According to the safety evaluation independent verification method for the passive characteristic of the third-generation nuclear power station, a software system suitable for the passive characteristic is established by verifying the operation data and the test data of the nuclear power station and combining an autonomous development/introduction/purchase program; establishing a database of a software system and a model for verifying the passive characteristic; wherein the database of the software system for verifying the passive characteristic comprises relevant data of single experiments and whole experiments for verifying heap type or similar heap type; independently verifying key accidents according to the selected passive characteristic design and combining with the design data information of the nuclear power station to obtain the identification and sequencing of key phenomena; the key phenomenon identification sequences are used for selecting the single experiment and the whole experiment design for software verification and uncertainty parameters; and carrying out calculation verification of passive characteristic superposition uncertainty analysis based on the related data, and optimizing and perfecting a phenomenon identification model according to accident analysis comparison or/and uncertainty analysis results. The invention forms a set of passive pressurized water reactor nuclear power plant key accident analysis and verification system, and can perform systematic verification work aiming at large advanced pressurized water reactors, small pressurized water reactors and autonomous programs.
In order to achieve the above object, an embodiment of a second aspect of the present invention provides a safety evaluation independent verification platform for passive characteristics of a third-generation nuclear power station, including:
the passive characteristic software system module is used for carrying out relevant analysis and calculation and establishing a passive characteristic software system suitable for the nuclear power station through verification of operation data and test data of the nuclear power station;
the verification database module is used for establishing a database of a software system and a model for verifying the passive characteristics; wherein the database of the software system for verifying the passive characteristic comprises relevant data of single experiments and whole experiments for verifying heap type or similar heap type;
the output module is used for designing and independently verifying key accidents according to the selected passive characteristics and combining the design data information of the nuclear power station to obtain the identification and sequencing of key phenomena; the key phenomenon identification sequences are used for selecting the single experiment design and the whole experiment for software verification and uncertainty parameters;
and the optimization module is used for carrying out calculation verification of passive characteristic superposition uncertainty analysis based on the related data and optimizing the phenomenon recognition model according to the accident analysis comparison and uncertainty analysis result.
The safety evaluation independent verification platform for the passive characteristic of the third-generation nuclear power station comprises a passive characteristic software system module, a safety evaluation independent verification platform and a safety evaluation independent verification platform, wherein the passive characteristic software system module is used for carrying out relevant analysis and calculation, and establishing a software system suitable for the passive characteristic through verification of nuclear power station operation data and test data; the verification database module is used for establishing a database of a software system and a model for verifying the passive characteristics; wherein the database of the software system for verifying the passive characteristic comprises relevant data of single experiments and whole experiments for verifying heap type or similar heap type; the output module is used for designing and independently verifying key accidents according to the selected passive characteristics and combining the design data information of the nuclear power station to obtain the identification and sequencing of key phenomena; the key phenomenon identification sequences are used for selecting the single experiment design and the whole experiment for software verification and uncertainty parameters; and the optimization module is used for carrying out calculation verification of passive characteristic superposition uncertainty analysis based on the related data and optimizing the phenomenon recognition model according to the accident analysis comparison and uncertainty analysis result. The invention forms a set of passive pressurized water reactor nuclear power plant key accident analysis and verification system, and can perform systematic verification work aiming at large advanced pressurized water reactors, small pressurized water reactors and autonomous programs.
The invention has the beneficial effects that:
and a reasonable safety evaluation independent verification system is provided for the passive characteristic of the third-generation nuclear power station. The method is applied to independent verification projects of national and first (CAP1400) key design benchmark accidents, the reasonable design and effectiveness of national and first passive safety systems (including passive core injection systems and passive containment cooling systems) are confirmed through verification analysis, the key design accidents PIRT are confirmed and perfected, and the national and first passive safety systems are beneficial to passing through relevant independent verification requirements and safety evaluation.
Additional aspects and advantages of the invention will be set forth in part in the description which follows and, in part, will be obvious from the description, or may be learned by practice of the invention.
Drawings
The foregoing and/or additional aspects and advantages of the present invention will become apparent and readily appreciated from the following description of the embodiments, taken in conjunction with the accompanying drawings of which:
FIG. 1 is a flow diagram of a safety evaluation independent verification system for non-kinetic energy characteristics of a nuclear power plant according to one embodiment of the invention;
FIG. 2 is a flow chart of a method for independently verifying safety evaluation of passive characteristics of a third generation nuclear power plant according to an embodiment of the invention;
fig. 3 is a schematic structural diagram of a safety evaluation independent verification platform for passive characteristics of a third-generation nuclear power plant according to an embodiment of the invention.
Detailed Description
Reference will now be made in detail to embodiments of the present invention, examples of which are illustrated in the accompanying drawings, wherein like or similar reference numerals refer to the same or similar elements or elements having the same or similar function throughout. The embodiments described below with reference to the drawings are illustrative and intended to be illustrative of the invention and are not to be construed as limiting the invention.
The following describes a safety evaluation independent verification method and platform for passive characteristics of a third-generation nuclear power station according to an embodiment of the present invention with reference to the accompanying drawings.
At present, a process for systematically developing independent verification of key accidents in a certain nuclear power station is not published internationally. No mechanism except the security and review mechanism in China undertakes systematic safety evaluation independent verification work, and a nuclear power station owner generally entrusts a third party to perform modeling analysis verification on individual key accidents. The invention forms a set of passive pressurized water reactor nuclear power plant key accident analysis and verification system, and can perform systematic verification work aiming at large advanced pressurized water reactors, small pressurized water reactors and autonomous programs.
Fig. 2 is a flowchart of a safety evaluation independent verification method for passive characteristics of a third-generation nuclear power plant according to an embodiment of the present invention.
As shown in fig. 2, the safety evaluation independent verification method for passive characteristics of a third-generation nuclear power station includes:
and step S1, establishing a software system suitable for passive characteristics by verifying the nuclear power station operation data and the test data and combining the self-development/introduction/purchase program.
Step S2, establishing a database of a software system and a model for verifying the passive characteristics; the database of the software system for verifying the passive characteristic comprises relevant data of single experiments and whole experiments for verifying the heap type or similar heap types.
Step S3, independently verifying key accidents and combining with design data information of the nuclear power station according to the selected passive characteristic design to obtain key phenomenon identification sequencing; and the key phenomenon identification sequences are used for designing the single experiment and the whole experiment for software verification and selecting uncertainty parameters.
And step S4, performing calculation verification of passive characteristic superposition uncertainty analysis based on the related data, and optimizing and perfecting the phenomenon identification model according to accident analysis comparison or/and uncertainty analysis results.
Fig. 1 is a flow chart of a safety evaluation independent verification system for non-kinetic energy characteristics of a nuclear power plant according to an embodiment of the invention, as shown in fig. 1:
further, in an embodiment of the present invention, the software system suitable for the passive characteristic is based on an analysis program approved by the international/domestic safety evaluation agency, and needs to pass verification of the nuclear power plant operation data and test data, especially verification of the passive characteristic.
Further, in one embodiment of the present invention, the nuclear power plant operational data and test data includes, but is not limited to, passive test data for similar reactor types, benchmark test data published by international nuclear power agencies, example subjects, and operational/test data for similar reactor type nuclear power plants.
Further, in one embodiment of the present invention, the analysis procedures approved by the international/national security review agency include, but are not limited to: the method comprises a core physical design checking program, an optimal estimation system program, other thermal hydraulic system analysis programs and a containment response analysis program.
Further, in an embodiment of the present invention, the optimizing and perfecting the phenomenon recognition model according to the comparison of the calculation results of different procedures of the accident analysis or/and the uncertainty analysis result includes: and establishing an accident analysis reference model according to the design data information of the nuclear power station, and carrying out node division confirmation and uncertainty analysis steps and analysis comparison of different program results based on the accident analysis reference model.
Further, in an embodiment of the present invention, the optimizing and perfecting the phenomenon recognition model according to the comparison of the calculation results of different procedures of the accident analysis or/and the uncertainty analysis result further includes:
and selecting uncertainty parameters based on the accident analysis reference model, and carrying out uncertainty analysis.
It can be understood that a set of software system suitable for passive characteristics is established through verification of nuclear power plant operation data and test data, wherein the nuclear power plant operation data and the test data include but are not limited to passive test data for similar reactor types, benchmark test data/example questions issued by international nuclear energy agencies such as OECD, IAEA and the like, operation/test data of nuclear power plants of similar reactor types, and the like.
It can be understood that a set of software system suitable for passive characteristics is established by verifying the operation data and the test data of the nuclear power station, the software system is suitable for verifying the software system and the database of the model of the passive characteristics, the database comprises relevant data of single experiments and overall experiments for verifying the reactor type or similar reactor types, the software system is suitable for computing and verifying the superposition uncertainty analysis of the passive characteristics, and a phenomenon recognition model is improved and optimized according to the accident analysis comparison and uncertainty analysis results to form a complete independent verification process; the method comprises the steps of designing independent verification key accidents according to selected passive characteristics, obtaining preliminary PIRT according to information such as detailed design data of the nuclear power station and judgment of experts, guiding single item and integral experimental design for software verification and selection of uncertainty parameters during calculation and verification by the PIRT, supplementing the PIRT again after calculation and verification for passive characteristic superposition uncertainty analysis are completed, and forming a credible safety evaluation independent verification system for the passive characteristics of the nuclear power station through certain iteration self-improvement in the whole process.
It is understood that the software system of the present invention is a whole set of analysis procedures approved by the international/domestic safety evaluation agency, including but not limited to core physics core design procedures, thermohydraulic system analysis procedures, and containment analysis procedures.
As an example, for example, independent verification direction and content are researched and designed according to passive system characteristics, independent verification key accidents are designed in a targeted manner, and a reference model of the nuclear power plant is established by adopting verified software according to key accident phenomenon identification (used for designing accident conditions and related assumptions) and third-generation nuclear power plant detailed engineering design parameters.
As another example, for PCS systems, for example, two-extreme DBA incidents are designed, and for PXS systems, a small break incident analysis spectrum is designed. And improving and optimizing the phenomenon recognition model according to the accident analysis comparison and uncertainty analysis result. And a complete set of safety evaluation independent verification system suitable for the passive characteristic of the third-generation nuclear power station is formed by combining the verified program and method, the verified content and reference model and the autonomous development and optimization improvement of the phenomenon recognition model.
According to the safety evaluation independent verification method for the passive characteristic of the third-generation nuclear power station, a software system suitable for the passive characteristic is established by verifying the operation data and the test data of the nuclear power station and combining an autonomous development/introduction/purchase program; establishing a software system for verifying the passive characteristic and a database of the model; the database of the software system for verifying the passive characteristic comprises relevant data of single experiments and whole experiments for verifying heap type or similar heap type; independently verifying key accidents according to the selected passive characteristic design and combining with the design data information of the nuclear power station to obtain the identification and sequencing of key phenomena; the method comprises the following steps of identifying and sequencing key phenomena, designing single experiments and overall experiments for software verification, and selecting uncertainty parameters; and carrying out calculation verification of passive characteristic superposition uncertainty analysis based on the related data, and optimizing and perfecting the phenomenon identification model according to accident analysis comparison or/and uncertainty analysis results. The invention forms a set of passive pressurized water reactor nuclear power plant key accident analysis and verification system, and can perform systematic verification work aiming at large advanced pressurized water reactors, small pressurized water reactors and autonomous programs.
Fig. 3 is a schematic structural diagram of a safety evaluation independent verification platform for passive characteristics of a third-generation nuclear power plant according to an embodiment of the invention.
As shown in fig. 3, the safety evaluation independent verification platform 10 for passive characteristics of a third-generation nuclear power plant includes:
a passive feature software architecture module 100, a verification database module 200, an output module 300, and an optimization module 400.
The passive characteristic software system module 100 is used for performing relevant analysis and calculation, and establishing a passive characteristic software system suitable for the nuclear power plant through verification of operation data and test data of the nuclear power plant;
the verification database module 200 is used for establishing a database of a software system and a model for verifying the passive characteristics; the database of the software system for verifying the passive characteristic comprises relevant data of single experiments and whole experiments for verifying the heap type or similar heap types;
the output module 300 is used for designing and independently verifying key accidents and combining design data information of the nuclear power station according to the selected passive characteristics to obtain key phenomenon identification sequencing; the key phenomenon identification and sequencing is used for single experiment design and whole experiment of software verification and selection of uncertainty parameters;
and the optimization module 400 is used for performing calculation verification of passive characteristic superposition uncertainty analysis based on the related data, and optimizing the phenomenon identification model according to the accident analysis comparison and uncertainty analysis result.
Further, the system also comprises an analysis module which is used for modeling and analyzing the nuclear device to be verified by adopting an analysis program approved by the international/domestic security evaluation organization.
Further, the operation data and the test data of the nuclear power station in the verification database module 200 comprise one or more of passive test data aiming at similar reactor types, benchmark test data issued by international nuclear power agencies, example questions and operation/test data of nuclear power stations of similar reactor types.
Further, the analysis program approved by the international/domestic security evaluation organization in the analysis module comprises: the core physical design checking program, the optimal estimation system program, the thermal hydraulic system analysis program and the containment response analysis program.
According to the safety evaluation independent verification platform for the passive characteristic of the third-generation nuclear power station, a passive characteristic software system module is used for carrying out relevant analysis and calculation, and a software system suitable for the passive characteristic is established through verification of running data and test data of the nuclear power station; the verification database module is used for establishing a database of a software system and a model for verifying the passive characteristics; the database of the software system for verifying the passive characteristic comprises relevant data of single experiments and whole experiments for verifying the heap type or similar heap types; the output module is used for designing and independently verifying key accidents according to the selected passive characteristics and combining the design data information of the nuclear power station to obtain the identification and sequencing of key phenomena; the key phenomenon identification and sequencing is used for single experiment design and whole experiment of software verification and selection of uncertainty parameters; and the optimization module is used for carrying out calculation verification of passive characteristic superposition uncertainty analysis based on the related data and optimizing the phenomenon recognition model according to the accident analysis comparison and uncertainty analysis result. The invention forms a set of passive pressurized water reactor nuclear power plant key accident analysis and verification system, and can perform systematic verification work aiming at large advanced pressurized water reactors, small pressurized water reactors and autonomous programs.
Furthermore, the terms "first", "second" and "first" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include at least one such feature. In the description of the present invention, "a plurality" means at least two, e.g., two, three, etc., unless specifically limited otherwise.
In the description herein, references to the description of the term "one embodiment," "some embodiments," "an example," "a specific example," or "some examples," etc., mean that a particular feature, structure, material, or characteristic described in connection with the embodiment or example is included in at least one embodiment or example of the invention. In this specification, the schematic representations of the terms used above are not necessarily intended to refer to the same embodiment or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments or examples. Furthermore, various embodiments or examples and features of different embodiments or examples described in this specification can be combined and combined by one skilled in the art without contradiction.
Although embodiments of the present invention have been shown and described above, it is understood that the above embodiments are exemplary and should not be construed as limiting the present invention, and that variations, modifications, substitutions and alterations can be made to the above embodiments by those of ordinary skill in the art within the scope of the present invention.
Claims (10)
1. A safety evaluation independent verification method for passive characteristics of a third-generation nuclear power station is characterized by comprising the following steps:
establishing a software system suitable for the passive characteristic by verifying the operation data and the test data of the nuclear power station and combining an autonomous development/introduction/purchase program;
establishing a database of a software system and a model for verifying the passive characteristic; wherein the database of the software system for verifying the passive characteristic comprises relevant data of single experiments and whole experiments for verifying heap type or similar heap type;
independently verifying key accidents according to the selected passive characteristic design and combining with the design data information of the nuclear power station to obtain the identification and sequencing of key phenomena; the key phenomenon identification sequences are used for selecting the single experiment and the whole experiment design for software verification and uncertainty parameters;
and carrying out calculation verification of passive characteristic superposition uncertainty analysis based on the related data, and optimizing and perfecting a phenomenon identification model according to accident analysis comparison or/and uncertainty analysis results.
2. The independent verification method for the safety evaluation of the passive characteristic of the third-generation nuclear power plant according to claim 1, characterized in that the software system suitable for the passive characteristic is based on an analysis program approved by international/domestic safety evaluation organizations and needs to pass verification of the nuclear power plant operation data and test data, especially verification of the passive characteristic.
3. The method for independently verifying the passive characteristic of the third-generation nuclear power plant according to claim 1, wherein the nuclear power plant operation data and test data include one or more of passive test data for a reactor-like type, benchmark test data issued by international nuclear power agencies, example subjects, and operation/test data of a reactor-like type nuclear power plant.
4. The independent verification method for the safety evaluation of the passive characteristic of the third-generation nuclear power plant according to claim 2, wherein the analysis program approved by the international/national safety evaluation agency comprises: the core physical design checking program, the system program of the optimal estimation, other thermal hydraulic system analysis programs and the containment response analysis program.
5. The method for independently verifying the passive characteristic safety evaluation of the third-generation nuclear power plant according to claim 1, wherein the optimizing and perfecting a phenomenon recognition model according to the comparison of results or/and the uncertainty analysis results of different accident analysis procedures comprises: and establishing an accident analysis reference model according to the nuclear power station design data information, and performing node division confirmation and uncertainty analysis steps and analysis comparison of different program results based on the accident analysis reference model.
6. The method for independently verifying the passive characteristic safety evaluation of a third-generation nuclear power plant according to claim 5, wherein the phenomena identification model is optimized and perfected according to the comparison of results or/and the uncertainty analysis results of different accident analysis procedures, and further comprising:
and selecting the uncertainty parameters based on the accident analysis reference model to carry out uncertainty analysis.
7. A safety evaluation independent verification platform for passive characteristics of a third-generation nuclear power station is characterized by comprising:
the passive characteristic software system module is used for carrying out relevant analysis and calculation and establishing a passive characteristic software system suitable for the nuclear power station through verification of operation data and test data of the nuclear power station;
the verification database module is used for establishing a database of a software system and a model for verifying the passive characteristics; wherein the database of the software system for verifying the passive characteristic comprises relevant data of single experiments and whole experiments for verifying heap type or similar heap type;
the output module is used for designing and independently verifying key accidents according to the selected passive characteristics and combining the design data information of the nuclear power station to obtain the identification and sequencing of key phenomena; the key phenomenon identification sequences are used for selecting the single experiment design and the whole experiment for software verification and uncertainty parameters;
and the optimization module is used for carrying out calculation verification of passive characteristic superposition uncertainty analysis based on the related data and optimizing the phenomenon recognition model according to the accident analysis comparison and uncertainty analysis result.
8. The platform for independently verifying the safety evaluation of the passive characteristic of a third-generation nuclear power plant according to claim 7, further comprising an analysis module for performing modeling analysis on a nuclear device to be verified using an analysis program approved by an international/national safety evaluation agency.
9. The platform of claim 7, wherein the nuclear power plant operation data and test data in the verification database module comprise one or more of passive test data for similar reactor types, benchmark test data published by the international nuclear power agency, example questions and operation/test data of nuclear power plants of similar reactor types.
10. The platform for independently verifying the safety evaluation of the passive characteristic of the third-generation nuclear power plant according to claim 8, wherein the analysis module comprises an analysis program approved by an international/national safety evaluation organization, and the analysis program comprises: the core physical design checking program, the optimal estimation system program, the thermal hydraulic system analysis program and the containment response analysis program.
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