Method and system for determining technical specification of sodium-cooled fast reactor nuclear power plant

Abstract

The embodiment of the invention relates to the technical field of prediction and optimization, in particular to a method and system for determining a technical specification of a sodium-cooled fast reactor nuclear power plant. In the first aspect, the embodiment of the invention provides the method for determining the technical specification of the sodium-cooled fast reactor nuclear power plant, the technical specification comprises normal operation limit values and conditions of the sodium-cooled fast reactor nuclear power plant, and the method comprises the following steps: S10: determining structures, systems and equipment included in the sodium-cooled fast reactor nuclear power plant; s20, determining a screening criterion for normal operation limit values and conditions of the sodium-cooled fast reactor nuclear power plant; and S30, screening the structures, the systems and the equipment in the step S10 according to the screening criterion determined in the step S20, and determining the technical specification of the sodium-cooled fast reactor nuclear power plant. In the second aspect, the embodiment of the invention provides a system suitable for determining the technical specification of the sodium-cooled fast reactor nuclear power plant. According to the determination and system, the efficiency of determining the technical specification of the sodium-cooled fast reactor nuclear power plant can be improved, and the reliability of guiding the safe operation of the nuclear power plant is enhanced.

Description

Technical Field

[0001] The embodiments of the present application relate to the technical field of prediction and optimization, and specifically to a method and system for determining the technical specifications of a sodium-cooled fast reactor nuclear power plant. Background Art

[0002] The statements herein merely provide background information related to the present application and do not necessarily constitute prior art.

[0003] The technical specification of a nuclear power plant is an upper-level technical document that must be followed by most technical documents, technical regulations and management procedures during the operation of a nuclear power plant. It specifies in detail the technical requirements, safety parameters and operating procedures of the nuclear power plant under normal operation and accident conditions. Strict compliance with the technical specification of a nuclear power plant is of great significance to ensuring the safety, economy and stability of the nuclear power plant.

[0004] Since there are currently no regulatory standards for the normal operating limits and conditions of sodium-cooled fast reactor nuclear power plants, and due to the inherent characteristics of fast reactors, it is impossible to refer to the standards formulated for other pressurized water reactors. Therefore, there is a technical gap in the existing technology for determining the technical specifications of sodium-cooled fast reactor nuclear power plants. Summary of the invention

[0005] A brief overview of the present application is provided below in order to provide a basic understanding of certain aspects of the present application. It should be understood that this overview is not an exhaustive overview of the present application. It is not intended to identify the key or important parts of the present application, nor is it intended to limit the scope of the present application. Its purpose is merely to present certain concepts in a simplified form as a prelude to a more detailed description discussed later.

[0006] In a first aspect, an embodiment of the present application provides a method for determining a technical specification of a sodium-cooled fast reactor nuclear power plant, wherein the technical specification includes normal operating limits and conditions of the sodium-cooled fast reactor nuclear power plant, and comprises the following steps: S10: determining the structures, systems and equipment included in the sodium-cooled fast reactor nuclear power plant; S20: determining screening criteria for normal operating limits and conditions of the sodium-cooled fast reactor nuclear power plant; S30: screening the structures, systems and equipment in step S10 according to the screening criteria determined in step S20, and determining the technical specification of the sodium-cooled fast reactor nuclear power plant.

[0007] In a second aspect, an embodiment of the present application provides a system suitable for determining a technical specification of a sodium-cooled fast reactor nuclear power plant, the technical specification including normal operating limits and conditions of the sodium-cooled fast reactor nuclear power plant, comprising: a first storage module, the first storage module being configured to store data of structures, systems and equipment included in the sodium-cooled fast reactor nuclear power plant and instruments for detecting the structures, systems and equipment; a second storage module, the second storage module being configured to store screening criteria for normal operating limits and conditions of the sodium-cooled fast reactor nuclear power plant; a judgment module, the judgment module screening the structures, systems and equipment and instruments in the first storage module according to the screening criteria in the second storage module; and an output module, the output module being configured to output the result of the judgment module to a predetermined location in a predetermined manner.

[0008] The determination method and system in the embodiments of the present application determine the normal operating limits and conditions of the nuclear power plant by determining clear screening criteria for the normal operating limits and conditions of the sodium-cooled fast reactor nuclear power plant, and then screen out the structures, systems and equipment that meet the screening criteria from all the structures, systems and equipment included in the sodium-cooled fast reactor nuclear power plant, and compile the technical specifications of the sodium-cooled fast reactor nuclear power plant according to the operability requirements of these equipment and structures, so as to improve the efficiency of determining the technical specifications of the sodium-cooled fast reactor nuclear power plant and enhance the reliability of the technical specifications for guiding the safe operation of the nuclear power plant. BRIEF DESCRIPTION OF THE DRAWINGS

[0009] Other objects and advantages of the present application will become apparent from the following description of the embodiments of the present application with reference to the accompanying drawings, and will help to provide a comprehensive understanding of the present application.

[0010] Figure 1 It is a flow chart of a method for determining technical specifications of a sodium-cooled fast reactor nuclear power plant according to an embodiment of the present application.

[0011] It should be noted that the drawings are not necessarily drawn to scale, but are merely shown in a schematic manner that does not affect the reader's understanding. DETAILED DESCRIPTION

[0012] Exemplary embodiments of the present application will be described below in conjunction with the accompanying drawings. For the sake of clarity and conciseness, not all features of the actual implementation are described in the specification. However, it should be understood that many implementation-specific decisions must be made in the process of developing any such actual implementation in order to achieve the developer's specific goals, such as meeting those constraints related to the system and business, and these constraints may vary from implementation to implementation. In addition, it should be understood that although the development work may be very complex and time-consuming, it is only a routine task for those skilled in the art who benefit from the content of this application.

[0013] It is also necessary to explain here that, in order to avoid obscuring the present application due to unnecessary details, only the device structure and / or processing steps closely related to the scheme according to the present application are shown in the accompanying drawings, while other details that are not very relevant to the present application are omitted.

[0014] The inventors of the present application discovered that since the sodium-cooled fast reactor is a reactor that uses liquid sodium as a coolant, its basic operating mode and other aspects are significantly different from those of a pressurized water reactor. When determining the technical specifications of a sodium-cooled fast reactor nuclear power plant, it is impossible to refer to and draw on the relevant technical requirements and safety parameters of the pressurized water reactor. There is a lack of clear screening criteria for whether each operating limit and condition needs to be written into the technical specifications. Therefore, it is difficult to accurately and efficiently determine the technical specifications of a sodium-cooled fast reactor nuclear power plant.

[0015] Based on this, an embodiment of the present application provides a method for determining a technical specification of a sodium-cooled fast reactor nuclear power plant, wherein the technical specification includes normal operating limits and conditions of the sodium-cooled fast reactor nuclear power plant, such as Figure 1 As shown, Figure 1 A flow chart showing a method for determining a technical specification of a sodium-cooled fast reactor nuclear power plant according to an embodiment of the present application is provided, the method comprising the following steps:

[0016] S10: Determine that the sodium-cooled fast reactor nuclear power plant includes structures, systems and equipment.

[0017] S20: Determine screening criteria for normal operating limits and conditions for sodium-cooled fast reactor nuclear power plants.

[0018] S30: Screen the structures, systems and equipment in step S10 according to the screening criteria determined in step S20, and determine the technical specifications of the sodium-cooled fast reactor nuclear power plant.

[0019] The method provided in the embodiment of the present application determines the limits and conditions for the normal operation of a sodium-cooled fast reactor nuclear power plant by determining clear screening criteria for the limits and conditions for normal operation of the nuclear power plant, and then screens out the structures, systems and equipment that meet the screening criteria from all the structures, systems and equipment included in the sodium-cooled fast reactor nuclear power plant, and compiles the technical specifications of the sodium-cooled fast reactor nuclear power plant according to the operability requirements of these structures, systems and equipment, so as to improve the efficiency of determining the technical specifications of the sodium-cooled fast reactor nuclear power plant and enhance the reliability of the technical specifications in guiding the safe operation of the nuclear power plant.

[0020] In some embodiments, in step S20, the screening criteria are as follows: during the operation of the sodium-cooled fast reactor nuclear power plant, by implementing the operating limits and conditions of the predetermined structures, systems and equipment required in the technical specifications in step S10, it can be ensured that the sodium-cooled fast reactor nuclear power plant is within the initial state range assumed by the accident analysis, then the technical specifications of the predetermined structures, systems and equipment are determined to be the technical specifications of the sodium-cooled fast reactor nuclear power plant, and the technical specifications include the operating limits and conditions for the normal operation of the predetermined structures, systems and equipment.

[0021] In this embodiment, the operating limits and conditions of the predetermined structures, systems and equipment required in the technical specifications in step S10 are implemented during the operation of the nuclear power plant, so that the operating limits and conditions that can ensure that the sodium-cooled fast reactor nuclear power plant is within the initial state range assumed in the accident analysis are incorporated into the operating limits and conditions of the technical specifications of the nuclear power plant, so as to follow the initial assumptions in the accident analysis, comprehensively consider the operating conditions that lead to nuclear power plant accidents, determine more reliable screening criteria, and thus improve the screening accuracy of the normal operating limits and conditions of the nuclear power plant.

[0022] For example, the accident analysis assumes that the reactor needs to have sufficient initial conditions such as shutdown depth and safety rod drop time. The technical specification needs to put forward technical requirements for the safety rod drop time and shutdown depth. Under accident conditions, the technical specification can be implemented to ensure that the sodium-cooled fast reactor can be in the initial state assumed by the accident analysis, thereby improving the reliability of the technical specification in guiding the safe operation of nuclear power plants.

[0023] In some embodiments, in step S20, the screening criteria are as follows: the operability of the predetermined equipment and predetermined structures determined as the success path in the accident analysis is determined as the technical specification of the sodium-cooled fast reactor nuclear power plant, and the technical specification includes the normal operating limits and conditions of the predetermined structures, systems and equipment; wherein, the success path refers to an important way used in the accident analysis to ensure reactor safety or mitigate accidents, and the operability of these structures, systems or components can ensure that the nuclear power plant remains in a safe state after the corresponding accident occurs.

[0024] In this embodiment, the operating limits and conditions required in the technical specifications of the predetermined equipment and predetermined structures that serve as successful paths in the accident analysis are incorporated into the technical specifications of the nuclear power plant to ensure that under accident conditions, the equipment and structures that can play a role in accident mitigation are in normal operating conditions, thereby enhancing the reliability of the technical specifications in guiding the safe operation of the nuclear power plant.

[0025] For example, in response to the large sodium water accident in the steam generator unique to the sodium-cooled fast reactor, the actuators that perform operations such as water drainage, nitrogen filling, and argon filling protection, which can play a role in accident mitigation, need to be in normal operating state. Therefore, the operating limits and conditions of the actuators that perform operations such as water drainage, nitrogen filling, and argon filling protection are included in the technical specifications of the sodium-cooled fast reactor nuclear power plant.

[0026] In some embodiments, in step S20, the screening criteria are as follows: in the event of a radioactive release accident, the operating limits and conditions of the predetermined structures, systems and equipment that can ensure the integrity of the barrier of the sodium-cooled fast reactor nuclear power plant and the shielding of the control room and ensure that the release of radioactivity is as low as possible are determined as the technical specifications of the sodium-cooled fast reactor nuclear power plant, and the technical specifications include the normal operating limits and conditions of the predetermined structures, systems and equipment. This is to further improve the screening accuracy of the normal operating limits and conditions of the nuclear power plant and enhance the reliability of the technical specifications in guiding the safe operation of the nuclear power plant.

[0027] For example, in a sodium-cooled fast reactor, the primary sodium purification system is directly connected to the main container. If the system leaks, the primary sodium will be released into the air, causing a radioactive sodium fire. Therefore, from the perspective of ensuring the integrity of the barrier of the sodium-cooled fast reactor nuclear power plant, it is necessary to require the operability of the isolation valve connecting the primary sodium purification system to the main container as a normal operating limit and condition in the technical specification to ensure normal isolation after a sodium leak occurs; from the perspective of control room shielding, it is necessary to require the operability of the filter pipeline of the air supply system as a normal operating limit and condition in the technical specification.

[0028] In some embodiments, in step S20, the screening criteria are as follows: the operating limits and conditions of the scheduled equipment and scheduled structures that are important to public health and safety are determined as the technical specifications of the sodium-cooled fast reactor nuclear power plant according to operating experience or probabilistic safety analysis, and the normal operating limits and conditions of the scheduled equipment and scheduled structures are included in the technical specifications. This ensures the basic protection of public health and safety during the operation of the nuclear power plant and further enhances the reliability of the technical specifications in guiding the safe operation of the nuclear power plant.

[0029] Furthermore, for the associated equipment or systems of the scheduled equipment and scheduled structures that are important to public health and safety, it is possible to analyze whether the scheduled equipment and scheduled structures can normally perform the safety assurance function when the associated equipment or system is in a state where it cannot operate normally. If so, there is no need to include the operating limits and conditions of the associated equipment or system in the technical specifications of the sodium-cooled fast reactor nuclear power plant. If not, it is necessary to include the operating limits and conditions of the associated equipment or system in the technical specifications of the sodium-cooled fast reactor nuclear power plant, so as to effectively screen the associated equipment or systems of the scheduled structures, systems and equipment, avoid redundancy, and further improve the screening accuracy of the normal operating limits and conditions of the nuclear power plant.

[0030] For example, according to operating experience or probabilistic safety analysis, the auxiliary systems of the power plant and the auxiliary systems of the safety system play an important role in ensuring public health and safety. Therefore, the operating limits and conditions of the auxiliary systems of the power plant and the auxiliary systems of the safety system are included in the technical specifications of the sodium-cooled fast reactor nuclear power plant; and the support system of the auxiliary system of the safety system has no role in ensuring public health and safety, and through analysis it is determined that when the support system cannot operate normally, its corresponding safety system can still perform the safety assurance function normally, so its operating limits and conditions do not need to be included in the technical specifications of the sodium-cooled fast reactor nuclear power plant.

[0031] In addition, according to operating experience, failure of the lubricating oil cooling system of the primary sodium pump will directly lead to the inability of the primary sodium pump to operate normally. Therefore, the operability of the lubricating oil cooling system of the primary sodium pump needs to be required as a normal operating limit and condition in the technical specification; and, if the sodium impurities in the primary circuit exceed the standard and the blockage temperature increases, long-term operation may cause blockage of the flow channel and affect the safety of the reactor. Therefore, the primary sodium blockage temperature needs to be required as a normal operating limit and condition in the technical specification.

[0032] In some embodiments, in step S20, the screening criteria are as follows: the predetermined structures, systems and equipment whose technical specifications are determined to be the technical specifications of the sodium-cooled fast reactor nuclear power plant according to any one of the above screening criteria are tested, and the operating limits and conditions of the instruments displayed in the main control room of the sodium-cooled fast reactor nuclear power plant by the test results are determined to be the technical specifications of the sodium-cooled fast reactor nuclear power plant. In order to ensure that the instruments used to test the predetermined structures, systems and equipment whose technical specifications are determined to be the technical specifications of the sodium-cooled fast reactor nuclear power plant according to any one of the above screening criteria are in normal operating state, thereby ensuring continuous monitoring of the operating conditions of the predetermined structures, systems and equipment, and further enhancing the reliability of the technical specifications for guiding the safe operation of the nuclear power plant.

[0033] For example, the shutdown depth of a sodium-cooled fast reactor needs to be determined by the number of control rods at the bottom of the core, so the control rod position indication system needs to be in normal operating state, and the control rod position indication system needs to be required as a normal operating limit and condition in the technical specification; the normal operating limit of the core outlet sodium temperature has been required in the technical specification, so the function of the core outlet sodium temperature thermocouple needs to be required accordingly in the technical specification.

[0034] An embodiment of the present application also provides a system suitable for determining the technical specifications of a sodium-cooled fast reactor nuclear power plant, wherein the technical specifications include the normal operating limits and conditions of the sodium-cooled fast reactor nuclear power plant, and the system includes: a first storage module, the first storage module is configured to store data of structures, systems and equipment included in the sodium-cooled fast reactor nuclear power plant and instruments for detecting the structures, systems and equipment; a second storage module, the second storage module is configured to store screening criteria for the normal operating limits and conditions of the sodium-cooled fast reactor nuclear power plant; a judgment module, the judgment module screens the structures, systems and equipment and instruments in the first storage module according to the screening criteria in the second storage module; and an output module, the output module is configured to output the results of the judgment module to a predetermined location in a predetermined manner.

[0035] The system provided by the embodiment of the present application uses a judgment module to determine the limits and conditions for normal operation of the nuclear power plant according to the screening criteria for the normal operation limits and conditions of the sodium-cooled fast reactor nuclear power plant stored in the second storage module, and then screens out the structures, systems and equipment that meet the normal operation limits and conditions from all the structures, systems and equipment included in the sodium-cooled fast reactor nuclear power plant stored in the first storage module, and outputs the results through the output module to compile the technical specifications of the sodium-cooled fast reactor nuclear power plant according to the operating limits and conditions of the structures, systems and equipment involved in the output results, thereby facilitating the improvement of the efficiency of determining the technical specifications of the sodium-cooled fast reactor nuclear power plant and enhancing the reliability of the technical specifications for guiding the safety work of the nuclear power plant.

[0036] The process of determining the technical specifications of a sodium-cooled fast reactor nuclear power plant in this application is further explained below with specific examples.

[0037] In this embodiment, the sodium-cooled fast reactor is a large-scale pool-type sodium-cooled fast reactor. The structures, systems and equipment included in the sodium-cooled fast reactor nuclear power plant are determined, and the screening criteria 1-5 for the normal operating limits and conditions of the sodium-cooled fast reactor nuclear power plant are determined as follows:

[0038] Screening criterion 1: During the operation of a sodium-cooled fast reactor nuclear power plant, by implementing the operating limits and conditions of the predetermined structures, systems and equipment required in the technical specifications in step S10, it can be ensured that the sodium-cooled fast reactor nuclear power plant is within the initial state range assumed in the accident analysis. The operating limits and conditions of the predetermined structures, systems and equipment are determined as the technical specifications of the sodium-cooled fast reactor nuclear power plant; Screening criterion 2: The operating limits and conditions of the predetermined structures, systems and equipment determined as the success path in the accident analysis are determined as the technical specifications of the sodium-cooled fast reactor nuclear power plant, where the success path refers to an important way to ensure reactor safety or mitigate accidents in the accident analysis. The operability of these structures, systems or components can ensure that the nuclear power plant remains in a safe state after the corresponding accident occurs; Screening criterion 3: In the event of a radioactive release accident, the operating limits and conditions of the planned structures, systems and equipment that can ensure the integrity of the barrier of the sodium-cooled fast reactor nuclear power plant and the shielding of the control room and ensure that the release of radioactivity is as low as possible are determined as the technical specifications of the sodium-cooled fast reactor nuclear power plant; Screening criterion 4: The operating limits and conditions of the planned structures, systems and equipment that are important to public health and safety based on operating experience or probabilistic safety analysis are determined as the technical specifications of the sodium-cooled fast reactor nuclear power plant; Screening criterion 5: The planned structures, systems and equipment whose technical specifications are determined as the technical specifications of the sodium-cooled fast reactor nuclear power plant by any of the above screening criteria are tested, and the operating limits and conditions of the instruments whose test results are displayed in the main control room of the sodium-cooled fast reactor nuclear power plant are determined as the technical specifications of the sodium-cooled fast reactor nuclear power plant.

[0039] The structures, systems and equipment of the sodium-cooled fast reactor nuclear power plant are screened according to the screening criteria 1-5, and the technical specifications of the sodium-cooled fast reactor nuclear power plant are compiled according to the operating limits and conditions of these structures, systems and equipment. The screening results and screening criteria are shown in Table 1 below:

[0040] Table 1 Screening results and screening criteria

[0041]

[0042]

[0043]

[0044]

[0045]

[0046] Regarding the embodiments of the present application, it should also be noted that, in the absence of conflict, the embodiments of the present application and the features therein can be combined with each other to obtain new embodiments.

[0047] The above are only specific implementation methods of the present application, but the protection scope of the present application is not limited thereto. The protection scope of the present application shall be based on the protection scope of the claims.

Claims

1. A method for determining a technical specification of a sodium-cooled fast reactor nuclear power plant, wherein the technical specification includes normal operating limits and conditions of the sodium-cooled fast reactor nuclear power plant, characterized in that: It includes the following steps: S10: Determine the structures, systems and equipment included in the sodium-cooled fast reactor nuclear power plant; S20: determining screening criteria for normal operating limits and conditions of the sodium-cooled fast reactor nuclear power plant; S30: Screening the structures, systems and equipment in step S10 according to the screening criteria determined in step S20 to determine the technical specifications of the sodium-cooled fast reactor nuclear power plant.

2. The determination method according to claim 1, characterized in that: In step S20, the screening criteria are as follows: During the operation of the sodium-cooled fast reactor nuclear power plant, by implementing the operating limits and conditions of the predetermined equipment and predetermined structures required in the technical specification in step S10, it is possible to ensure that the sodium-cooled fast reactor nuclear power plant is within the initial state range assumed by the accident analysis, then the technical specification where the predetermined equipment and the predetermined structure are located is determined to be the technical specification of the sodium-cooled fast reactor nuclear power plant, and the technical specification includes the normal operating limits and conditions of the predetermined equipment and the predetermined structure.

3. The determination method according to claim 1, characterized in that: In step S20, the screening criteria are as follows: The operability of the predetermined structures, systems and equipment as the success path determined in the accident analysis is determined as the technical specification of the sodium-cooled fast reactor nuclear power plant, and the technical specification includes the normal operating limits and conditions of the predetermined structures, systems and equipment, Among them, the success path refers to the important way used in accident analysis to ensure reactor safety or mitigate accidents. The operability of these structures, systems or components can ensure that the nuclear power plant remains in a safe state after a corresponding accident occurs.

4. The determination method according to claim 1, characterized in that: In step S20, the screening criteria are as follows: In the event of a radioactive release accident, the operating limits and conditions of the predetermined structures, systems and equipment that can ensure the integrity of the barrier of the sodium-cooled fast reactor nuclear power plant and the shielding of the control room and ensure that the release of radioactivity is as low as possible are determined as the technical specifications of the sodium-cooled fast reactor nuclear power plant, and the technical specifications include the normal operating limits and conditions of the predetermined equipment and structures.

5. The determination method according to claim 1, characterized in that: In step S20, the screening criteria are as follows: The technical specifications of the predetermined equipment and structures that are important to public health and safety according to operating experience or probabilistic safety analysis are determined as the technical specifications of the sodium-cooled fast reactor nuclear power plant, and the technical specifications include the normal operating limits and conditions of the predetermined equipment and structures.

6. The determination method according to any one of claims 2 to 5, characterized in that: In step S20, the screening criteria are as follows: The predetermined equipment and predetermined structures determined as their technical specifications in any one of claims 2-5 are tested, and the operating limits and conditions of the instruments displayed in the main control room of the sodium-cooled fast reactor nuclear power plant as a result of the test are determined as the technical specifications of the sodium-cooled fast reactor nuclear power plant.

7. A system for determining a technical specification of a sodium-cooled fast reactor nuclear power plant, wherein the technical specification includes normal operating limits and conditions of the sodium-cooled fast reactor nuclear power plant, characterized in that: It includes: A first storage module, wherein the first storage module is configured to store data of structures, systems and equipment included in the sodium-cooled fast reactor nuclear power plant and instruments for detecting the structures, systems and equipment; a second storage module, the second storage module being configured to store screening criteria for normal operating limits and conditions of the sodium-cooled fast reactor nuclear power plant; A judgment module, wherein the judgment module screens the structures, systems and equipment and the instruments in the first storage module according to the screening criteria in the second storage module; An output module is configured to output the result of the judgment module to a predetermined location in a predetermined manner.

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