Development method of heat pipe reactor system analysis program

Abstract

The invention provides a heat pipe reactor system analysis program development method. Comprising the steps that the application range of a system analysis program is determined, phenomena needing to be simulated in the application range are recognized, the phenomena are graded according to the importance degree, and a phenomenon recognition and sorting table is obtained; function requirements of the system analysis program are determined according to the phenomenon identification and sorting table; theoretical models of the reactor core, the heat pipe and the heat exchanger are established according to the function requirements and the performance requirements, and the performance requirements comprise the calculation efficiency requirement and the calculation stability requirement; detailed design of a system analysis program is carried out according to the theoretical model to obtain the system analysis program, and the system structure of the system analysis program is designed according to the theoretical model and comprises a main program module, an input module, an output module, a physical property module, a system module and a numerical solution module, wherein the system module comprises a reactor core calculation module, a heat pipe calculation module and a heat exchanger calculation module; a programming language is adopted to carry out development and programming on each module in the system structure.

Description

Technical Field

[0001] The invention mainly relates to the technical field of nuclear reactors, and in particular to a method for developing a heat pipe reactor system analysis program. Background Art

[0002] At present, large pressurized water reactor nuclear power technology has matured and occupies a large proportion in the energy structure of my country and even the world. Compared with pressurized water reactors, heat pipe reactors generally use all-solid cores and use heat pipes as passive heat removal devices. Since the reactor structure and heat transfer mechanism are different from those of pressurized water reactors, the system analysis program of pressurized water reactors is no longer applicable.

[0003] To solve the above problems, it is necessary to develop a heat pipe reactor system analysis program for safety analysis based on the overall structure and heat transfer mechanism of the heat pipe reactor, and to carry out research on solid-state core thermal conductivity and precise simulation of heat pipe performance. Summary of the invention

[0004] Aiming at the problem that a heat pipe reactor lacks a system analysis program, the present invention proposes a method for developing a system analysis program for a heat pipe reactor.

[0005] In order to solve the above technical problems, the present invention provides a method for developing a heat pipe reactor system analysis program, including: determining the application scope of the system analysis program, identifying the phenomena that need to be simulated within the application scope, grading the phenomena according to their importance, and obtaining a phenomenon identification and ranking table; determining the functional requirements of the system analysis program according to the phenomenon identification and ranking table; establishing theoretical models of the core, heat pipe and heat exchanger respectively according to the functional requirements and performance requirements, and the performance requirements include calculation efficiency requirements and calculation stability requirements; performing detailed design of the system analysis program according to the theoretical model to obtain the system analysis program, including: designing the system analysis program architecture according to the theoretical model, the system architecture includes a main program module, an input module, an output module, a physical property module, a system module and a numerical solution module, wherein the system module includes a core calculation module, a heat pipe calculation module and a heat exchanger calculation module; and using a programming language to develop and program each module in the architecture.

[0006] Optionally, the functional requirements of the system analysis program are determined based on the phenomenon identification and ranking table, including: the system analysis program should be able to best or conservatively simulate the phenomena graded as "high" in the phenomenon identification and ranking table, be able to reasonably simulate the phenomena graded as "medium" in the phenomenon identification and ranking table, and be able to simulate the phenomena graded as "low" in the phenomenon identification and ranking table.

[0007] Optionally, the theoretical model of the core includes a core thermal model, a core physical calculation model and a core mechanical calculation model.

[0008] Optionally, establishing the core thermal model according to the computational efficiency requirement includes: equating the heat pipe and the surrounding fuel rods into one channel, and expanding the channel to the entire stack by connecting multiple channels in parallel to establish the core thermal model.

[0009] Optionally, the channel is a regular polygon, and the core is composed of a plurality of regular polygons closely arranged in a honeycomb form.

[0010] Optionally, establishing the core physics calculation model according to the calculation efficiency requirement includes: using a point reactor neutron kinetic model as the core physics calculation model.

[0011] Optionally, establishing the theoretical model of the heat pipe according to the computational stability requirement includes: establishing the theoretical model of the heat pipe using a multi-scale coupling method combining transient and steady states.

[0012] Optionally, the core calculation module includes a core physics calculation module, a core thermal calculation module, and a core mechanics calculation module.

[0013] Optionally, the core physics calculation module includes a point reactor neutron dynamics calculation module, a reactivity feedback module and a decay heat calculation module.

[0014] Optionally, the core thermal calculation module includes a fuel zone heat conduction calculation module, a cladding, a matrix and other heat conduction calculation modules, a heat transfer calculation module between adjacent channels and a heat conduction calculation module for other heat dissipation components.

[0015] Optionally, the method further includes: testing and verifying the heat pipe reactor system analysis program.

[0016] Optionally, testing and verifying the heat pipe reactor system analysis program includes: listing a test matrix according to the functional requirements, the test matrix including multiple test cases; determining whether the test matrix completely covers the phenomena in the phenomenon identification and sorting table, and if so, using the test matrix to verify the integrity of the program function.

[0017] Optionally, the comparison data of the test cases in each test matrix include theoretical solutions, calculation results of other mature programs and test data.

[0018] Optionally, the application scope includes scheme design, test pre-analysis and safety analysis of heat pipe reactors.

[0019] Compared with the prior art, the present invention has the following advantages:

[0020] The method for developing a heat pipe reactor system analysis program of the present invention uses a heat pipe reactor phenomenon identification and ranking table as a program development guideline for the design features and operating characteristics of the heat pipe reactor, and guides the entire program development process, including steps such as demand analysis, theoretical modeling, detailed design, and test verification. The method can be used to develop a new reactor system analysis program to ensure the integrity of requirements, accessibility of interfaces, and adequacy of verification during program development. By modeling key phenomena in key equipment of the heat pipe reactor, the modeling scope involves various components of the heat pipe reactor system, including the core, heat pipes, and heat exchangers. The physical phenomena described by the model cover core physics, core thermals, heat exchange of heat pipes, heat exchanger cycles, etc., thereby realizing the development of a heat pipe reactor safety analysis tool. The developed heat pipe reactor system analysis program is used for heat pipe reactor safety analysis to improve the safety and reliability of the reactor. BRIEF DESCRIPTION OF THE DRAWINGS

[0021] The accompanying drawings are included to provide a further understanding of the present application. They are included and constitute a part of the present application. The accompanying drawings illustrate embodiments of the present application and together with the present specification serve to explain the principles of the present invention. In the accompanying drawings:

[0022] Figure 1 is a flow chart of a method for developing a heat pipe reactor system analysis program according to an embodiment of the present invention.

[0023] Figure 2 It is a schematic diagram of the functional requirements determined based on the phenomenon identification and ranking table.

[0024] Figure 3A is a schematic diagram of a core according to an embodiment of the present invention.

[0025] Figure 3B yes Figure 3A Schematic diagram of a single channel in .

[0026] Figure 4 Schematic diagram of multi-time scale coupling of a heat pipe according to an embodiment of the present invention.

[0027] Figure 5 4 is a schematic diagram of the structure of a system analysis program according to an embodiment of the present invention.

[0028] Figure 6 yes Figure 5 A flowchart of the execution process of a system analysis program according to an embodiment. DETAILED DESCRIPTION

[0029] In order to more clearly illustrate the technical solutions of the embodiments of the present application, the following is a brief introduction to the drawings required for the description of the embodiments. Obviously, the drawings described below are only some examples or embodiments of the present application. For ordinary technicians in this field, the present application can also be applied to other similar scenarios based on these drawings without creative work. Unless it is obvious from the language environment or otherwise explained, the same reference numerals in the figures represent the same structure or operation.

[0030] Flowcharts are used in the present application to illustrate the operations performed by the system according to the embodiments of the present application. It should be understood that the preceding or following operations are not necessarily performed accurately in order. On the contrary, various steps may be processed in reverse order or simultaneously. At the same time, other operations may be added to these processes, or one or more operations may be removed from these processes.

[0031] The present invention aims to solve the problem of lack of system analysis program for heat pipe reactors and proposes a method for developing a system analysis program for heat pipe reactors. The system analysis program development method models key phenomena in key equipment of heat pipe reactors, and the modeling scope involves various components of the heat pipe reactor system, including core, heat pipes and heat exchangers. The physical phenomena described by the model cover core physics, core thermals, heat pipe heat exchange, heat exchanger cycle, etc., to achieve the development of heat pipe reactor safety analysis tools. The developed heat pipe reactor system analysis program is used for heat pipe reactor safety analysis to improve the safety and reliability of the reactor.

[0032] The present invention proposes a system analysis software development method for heat pipe reactors. First, the standard for guiding software development is determined. The present invention adopts Phenomena Identification and Ranking Table (PIRT) as a standard to guide the entire process and full scope of software development. PIRT is an analysis method that identifies and ranks the phenomena involved in the working conditions of nuclear power plants according to their importance through information collation and expert judgment. This method allows research to focus on analyzing key phenomena and improve the efficiency of safety analysis. Among them, the entire software development process includes demand analysis, theoretical model, detailed design of theoretical model and test verification. Using PIRT to guide the entire process of program development ensures that program development covers all elements of the reactor, and ensures the integrity of program demand analysis, accessibility of interfaces and adequacy of verification.

[0033] Figure 1 FIG. 1 is a flow chart of a method for developing a heat pipe reactor system analysis program according to an embodiment of the present invention. Figure 1 As shown, the method 100 for developing a heat pipe reactor system analysis program includes the following steps:

[0034] Step S11: determine the application scope of the system analysis program, identify the phenomena that need to be simulated within the application scope, classify the phenomena according to their importance, and obtain a phenomenon identification and ranking table.

[0035] Optionally, the application scope of the system analysis program includes but is not limited to test pre-analysis, scheme design and safety analysis. When identifying the phenomena that need to be simulated within the scope of application, it is necessary to cover different operating modes of the heat pipe reactor, such as normal operating conditions and accident conditions. Among them, normal operating conditions should include starting and stopping the reactor, power conversion, etc. The accident conditions are determined according to the accident list of the heat pipe reactor, and can calculate the different conditions in the accident list of the heat pipe reactor, set the shutdown and protection signals according to the accident process, and switch the dedicated system to realize the accident sequence control function.

[0036] Taking the application scope of safety analysis as an example, first, the structure of the heat pipe reactor is studied. The heat pipe reactor is usually divided into a reactor system and a thermoelectric conversion system. The reactor system includes a core (including fuel rods, a matrix, a reflective layer, a drum, a safety rod, a shielding layer), a heat pipe, a heat exchanger, a stack, etc.; the thermoelectric conversion system has different equipment according to different power conversion methods, generally including a regenerator, a gas turbine, a compressor and a motor. The evaporation section of the high-temperature heat pipe is inside the core, and the condensation section is in the heat exchanger, which exports heat from the reactor system to the thermoelectric / thermodynamic conversion system. Identify the phenomena that need to be simulated by each device of the heat pipe reactor (for example, fuel rods, heat pipes, etc.) during the safety analysis process, classify the phenomena according to their importance, and obtain a phenomenon identification and ranking table. Table 1 is a phenomenon identification and ranking table of a heat pipe reactor in an embodiment of the present invention. As shown in Table 1, phenomena related to fuel rods include reactivity feedback, power and flux distribution, decay heat, and "fuel-cladding" gap heat conduction. Phenomena related to heat pipes include heat pipe failure and heat pipe deformation. Each phenomenon has a corresponding rating, which includes H (high), M (medium) and L (low).

[0037] Table 1 Identification and sorting of heat pipe reactor phenomena

[0038]

[0039] Step S12: Determine the functional requirements of the system analysis program according to the phenomenon identification and ranking table.

[0040] Among them, the determined functional requirements need to cover all phenomena in the phenomenon identification and ranking table, and different processing methods are adopted for different phenomenon levels. Optionally, the functional requirements of the system analysis program determined according to the phenomenon identification and ranking table include: the system analysis program should have the best or conservative simulation of the phenomena graded as "high" in the phenomenon identification and ranking table, have a reasonable simulation of the phenomena graded as "medium" in the phenomenon identification and ranking table, and have the simulation of the phenomena graded as "low" in the phenomenon identification and ranking table. Figure 2It is a schematic diagram of the functional requirements determined based on the phenomenon identification and sorting table. Figure 2 As shown, the functional requirement for the "power and flux distribution" phenomenon classified as "H" is core physics calculation, the functional requirement for the "decay heat" phenomenon classified as "H" is decay heat calculation, and the functional requirement for the "heat pipe deformation" phenomenon classified as "M" is heat pipe calculation. Each phenomenon in the phenomenon identification and sorting table has a corresponding functional requirement.

[0041] Step S13: Establish theoretical models of the core, heat pipe and heat exchanger respectively according to functional requirements and performance requirements. The performance requirements include computational efficiency requirements and computational stability requirements.

[0042] The modeling scope is determined according to the functional requirements, and the modeling scope includes the reactor system and / or the thermoelectric conversion system. Taking the reactor system as an example, the modeling scope of the program development method is mainly the various equipment of the reactor system, including the core, heat pipe and heat exchanger. In another embodiment, the same method is also used to model and analyze the equipment of the thermoelectric conversion system or other systems. Taking the reactor system as an example, theoretical models of the core, heat pipe and heat exchanger are established respectively. Reference Figure 2 From the demand analysis, it can be seen that the theoretical model of the core needs to include the core thermal model, the core physics calculation model and the core mechanics calculation model.

[0043] Users generally have requirements for the performance of system analysis programs, including computational efficiency and computational stability. To ensure computational efficiency, this application treats the heat pipe and the surrounding fuel rods as one channel, expands to the entire reactor through parallel multi-channels, and establishes a core thermal model. Figure 3A is a schematic diagram of a core according to an embodiment of the present invention. Figure 3B yes Figure 3A Schematic diagram of a single channel in . Figure 3A As shown, the core is composed of multiple single channels A arranged closely in a honeycomb form. The core includes fuel rods 31, a matrix 32 and a heat pipe 33. The fuel rod 31 includes a fuel element 311, a fuel air gap 312 and a fuel cladding 313. The heat pipe 33 includes a heat pipe steam chamber space 331, a heat pipe wire mesh and a pipe wall 332 and a heat pipe air gap 333, and the heat pipe 33 and the fuel rods surrounding the heat pipe 33 are equivalent to a single channel A. In this embodiment, the channel form composed of the single channel A is a "hexagon", and in some embodiments, the channel form can also be other regular polygons. In order to ensure the computational efficiency of the heat pipe reactor system analysis program, the present invention does not model the core geometry in detail, but treats the heat pipe and the surrounding fuel rods as a whole, equivalent to a channel, and expands to the whole stack through parallel multi-channels to perform a full stack solution.

[0044] Considering the small and compact core characteristics of the heat pipe reactor and the computational efficiency, a point-pile neutron kinetic model is used as the core physics calculation model instead of a sophisticated three-dimensional space-time kinetic model. In order to meet the program's application in different scenarios, various forms such as point-pile neutron kinetic models and input boundaries are established for the "power and flux distribution" phenomenon, which are used for heat pipe reactor safety analysis and non-nuclear overall performance tests.

[0045] Optionally, a multi-scale coupling method combining transient and steady states is used to establish a theoretical model of the heat pipe. The use of a multi-scale coupling method combining transient and steady states can improve the calculation instability problem of the heat pipe model and increase the calculation speed of the program. Figure 4 FIG. 1 is a schematic diagram of multi-time scale coupling of a heat pipe according to an embodiment of the present invention. Figure 4 As shown in the figure, the heat pipe includes a steam chamber, a liquid wick and a pipe wall. Steady-state calculation is used in the steam chamber, and transient calculation is used in the liquid wick and the pipe wall. In transient calculation, relevant parameters are obtained from steady-state calculation, and boundary conditions are updated to steady-state calculation after transient calculation is completed.

[0046] Step S14: Perform detailed design of the system analysis program according to the theoretical model to obtain the system analysis program.

[0047] The detailed design of the system analysis procedure based on the theoretical model includes:

[0048] Step S141: Design the architecture of the system analysis program according to the theoretical model.

[0049] In order to balance the computational efficiency and computational accuracy, the system analysis program of this application adopts a multi-dimensional modeling method of overall one-dimensional plus local refinement. The theoretical model of the heat pipe reactor is divided into a core model, a heat pipe model and a heat exchanger model, wherein the core model is further divided into a core physical calculation model, a core thermal model and a core mechanical model. Correspondingly, the following system architecture can be established: the system architecture includes a main program module, an input module, an output module, a physical property module, a system module and a numerical solution module, wherein the system module includes a core physical calculation module, a core thermal calculation module and a core mechanical calculation module, a heat pipe calculation module and a heat exchanger calculation module.

[0050] Step S142: Use a programming language to develop and program each module in the architecture.

[0051] Using modular development method, the heat pipe reactor system analysis program is divided into multiple modules, and each module is developed and programmed using a suitable programming language, which has good maintainability and scalability. Figure 5 FIG. 1 is a schematic diagram of the structure of a system analysis program according to an embodiment of the present invention. Figure 5As shown, the system analysis program 500 includes a main program module (not shown), an input module 51, an output module 52, a physical property module 53, a system module 54 and a numerical solution module (not shown). Among them, the system module 54 is divided into a core physics calculation module 541, a core thermal calculation module 542, a core mechanics calculation module 543, a heat pipe calculation module 544 and a heat exchanger calculation module 545. Among them, the core physics calculation module 541 includes a point pile neutron dynamics calculation module (referred to as the point pile calculation module) 5411, a reactivity feedback module 5412, and a decay heat calculation module 5413. The core thermal calculation module 542 includes a fuel area heat conduction calculation module 5421, a cladding, a matrix and other heat conduction calculation modules 5422, a heat transfer calculation module 5423 between adjacent channels and a heat conduction calculation module 5424 for other heat dissipation components. Optionally, the heat pipe calculation module 544 includes a heat pipe thermal resistance network module 5441, a heat pipe heat transfer limit module 5442, and a heat pipe pseudo thermal conductivity module 5443. Optionally, the heat exchanger calculation module 545 includes a main heat exchanger module 5451 and a residual heat exchanger module 5452. The programming language is used to develop and program each module to complete the detailed program design.

[0052] In order to facilitate the understanding of the system analysis procedure of this application, Figure 6 yes Figure 5A flowchart of the execution process of the system analysis program of an embodiment. At the beginning, the core geometry, thermal parameters, core physical calculation mode and heat transfer mode of the heat exchanger are read in through the input module 51. Optionally, the input module 51 reads the core geometry, thermal parameters, core physical calculation mode and heat transfer mode of the heat exchanger in the form of an input card. In other embodiments, the input module 51 can also input the core geometry, thermal parameters, core physical calculation mode and heat transfer mode of the heat exchanger through an interface graphic. The core physical calculation module 541 calculates the core parameters, which include but are not limited to neutron flux density and power. The core parameters are sent to the core thermal calculation module 542. The core thermal calculation module 542 forwards the core parameters to the fuel zone heat conduction calculation module 5421, the cladding, matrix and other heat conduction calculation modules 5422, the adjacent channel heat transfer calculation module 5423 and the other heat dissipation component heat conduction calculation module 5424 to calculate the core temperature and the heat that can be generated. The core thermal calculation module 542 sends the core temperature to the core mechanical calculation module 543 to calculate the core mechanical parameters, including but not limited to stress and variable force. The heat pipe calculation module 544 receives the core temperature and the heat that can be generated from the core thermal calculation module 542, and calculates the heat that can be transferred to the heat exchanger calculation module 545. The heat exchanger calculation module 545 calculates the heat after heat exchange and the core temperature. The whole process is a continuous iterative process. When all parameters in the calculation module meet the convergence conditions, that is, the parameter iteration residual is less than a smaller value, the calculation of the next moment is entered. When the calculation reaches the set time, the calculation ends and the calculation parameters are output. The system analysis program of the present invention is used for safety analysis of various accidents and transient conditions of heat pipe reactors to improve the safety and reliability of reactors.

[0053] In some embodiments, the method for developing a heat pipe reactor system analysis program further includes testing and verifying the heat pipe reactor system analysis program.

[0054] Optionally, testing and verifying the heat pipe reactor system analysis program includes: listing a test matrix according to functional requirements, the test matrix including multiple test cases; judging whether the test matrix completely covers the phenomena in the heat pipe reactor phenomenon identification and sorting table, and if so, using the test matrix to verify the integrity of the program function. Optionally, the comparison data of the test cases in each test matrix can be theoretical solutions, calculation results of other mature programs, and test data.

[0055] The heat pipe reactor system analysis program development method of the present invention uses the heat pipe reactor phenomenon identification and ranking table as the program development guiding principle for the design features and operating characteristics of the heat pipe reactor, and guides the entire program development process, including steps such as demand analysis, theoretical model, detailed design and test verification. The method can be used to develop a new reactor system analysis program to ensure the integrity of the requirements, accessibility of the interface and adequacy of verification during the program development process. The system analysis program of the present invention uses an equivalent single channel for full-heap modeling in view of the characteristics of the heat pipe reactor to improve the calculation efficiency.

[0056] The basic concepts have been described above. Obviously, for those skilled in the art, the above invention disclosure is only used as an example and does not constitute a limitation of the present application. Although not explicitly stated herein, those skilled in the art may make various modifications, improvements and amendments to the present application. Such modifications, improvements and amendments are suggested in the present application, so such modifications, improvements and amendments still belong to the spirit and scope of the exemplary embodiments of the present application.

[0057] At the same time, the present application uses specific words to describe the embodiments of the present application. For example, "one embodiment", "an embodiment", and / or "some embodiments" refer to a certain feature, structure or characteristic related to at least one embodiment of the present application. Therefore, it should be emphasized and noted that "one embodiment" or "an embodiment" or "an alternative embodiment" mentioned twice or more in different positions in this specification does not necessarily refer to the same embodiment. In addition, some features, structures or characteristics in one or more embodiments of the present application can be appropriately combined.

[0058] Some aspects of the present application may be performed entirely by hardware, entirely by software (including firmware, resident software, microcode, etc.), or by a combination of hardware and software. The above hardware or software may be referred to as "data blocks", "modules", "engines", "units", "components" or "systems". The processor may be one or more application specific integrated circuits (ASICs), digital signal processors (DSPs), digital signal processing devices (DAPDs), programmable logic devices (PLDs), field programmable gate arrays (FPGAs), processors, controllers, microcontrollers, microprocessors, or combinations thereof. In addition, various aspects of the present application may be expressed as computer products located in one or more computer-readable media, which include computer-readable program codes. For example, computer-readable media may include, but are not limited to, magnetic storage devices (e.g., hard disks, floppy disks, tapes ...), optical disks (e.g., compact disks CDs, digital versatile disks DVDs ...), smart cards, and flash memory devices (e.g., cards, sticks, key drives ...).

[0059] A computer-readable medium may include a propagated data signal containing computer program code, such as in baseband or as part of a carrier wave. The propagated signal may have a variety of manifestations, including electromagnetic, optical, etc., or a suitable combination. A computer-readable medium may be any computer-readable medium other than a computer-readable storage medium, which may be connected to an instruction execution system, device or apparatus to communicate, propagate or transmit a program for use. The program code on the computer-readable medium may be propagated via any suitable medium, including radio, cable, fiber optic cable, radio frequency signal, or similar medium, or any combination of the above mediums.

[0060] Similarly, it should be noted that in order to simplify the description of the disclosure of this application and thus help understand one or more embodiments of the invention, in the above description of the embodiments of this application, multiple features are sometimes combined into one embodiment, figure or description thereof. However, this disclosure method does not mean that the features required by the object of this application are more than the features mentioned in the claims. In fact, the features of the embodiments are less than all the features of the single embodiment disclosed above.

[0061] In some embodiments, numbers describing the number of components and attributes are used. It should be understood that such numbers used in the description of the embodiments are modified by the modifiers "about", "approximately" or "substantially" in some examples. Unless otherwise specified, "about", "approximately" or "substantially" indicate that the numbers are allowed to vary by ±20%. Accordingly, in some embodiments, the numerical parameters used in the specification and claims are approximate values, which may change according to the required features of individual embodiments. In some embodiments, the numerical parameters should take into account the specified significant digits and adopt the general method of retaining digits. Although the numerical domains and parameters used to confirm the breadth of their range in some embodiments of the present application are approximate values, in specific embodiments, the setting of such numerical values ​​is as accurate as possible within the feasible range.

[0062] Although the present application has been described with reference to the current specific embodiments, ordinary technicians in this technical field should recognize that the above embodiments are only used to illustrate the present application, and various equivalent changes or substitutions may be made without departing from the spirit of the present application. Therefore, as long as the changes and modifications to the above embodiments are within the essential spirit of the present application, they will fall within the scope of the claims of the present application.

[0063] As shown in this application and claims, unless the context clearly indicates an exception, the words "a", "an", "an" and / or "the" do not refer to the singular and may also include the plural. Generally speaking, the terms "include" and "comprise" only indicate the inclusion of the steps and elements that have been clearly identified, and these steps and elements do not constitute an exclusive list. The method or device may also include other steps or elements.

[0064] Unless otherwise specifically stated, the relative arrangement, numerical expressions and numerical values ​​of the parts and steps set forth in these embodiments do not limit the scope of the present application. At the same time, it should be understood that, for ease of description, the sizes of the various parts shown in the accompanying drawings are not drawn according to the actual proportional relationship. The technology, method and equipment known to those of ordinary skill in the relevant field may not be discussed in detail, but in appropriate cases, the technology, method and equipment should be considered as a part of the authorization specification. In all examples shown and discussed here, any specific value should be interpreted as being merely exemplary, rather than as a limitation. Therefore, other examples of exemplary embodiments may have different values. It should be noted that similar reference numerals and letters represent similar items in the following drawings, so that once a certain item is defined in an accompanying drawing, it does not need to be further discussed in subsequent drawings.

[0065] In the description of the present application, it should be understood that the directions or positional relationships indicated by directional words such as "front, back, up, down, left, right", "lateral, vertical, perpendicular, horizontal" and "top, bottom" are usually based on the directions or positional relationships shown in the drawings, and are only for the convenience of describing the present application and simplifying the description. Unless otherwise specified, these directional words do not indicate or imply that the device or element referred to must have a specific direction or be constructed and operated in a specific direction, and therefore cannot be understood as limiting the scope of protection of the present application; the directional words "inside and outside" refer to the inside and outside relative to the contours of each component itself.

[0066] For ease of description, spatially relative terms such as "above", "above", "on the upper surface of", "above", etc. may be used here to describe the spatial positional relationship between a device or feature and other devices or features as shown in the figure. It should be understood that spatially relative terms are intended to include different orientations of the device in use or operation in addition to the orientation described in the figure. For example, if the device in the accompanying drawings is inverted, the device described as "above other devices or structures" or "above other devices or structures" will be positioned as "below other devices or structures" or "below other devices or structures". Thus, the exemplary term "above" can include both "above" and "below". The device can also be positioned in other different ways (rotated 90 degrees or in other orientations), and the spatially relative descriptions used here are interpreted accordingly.

[0067] In addition, it should be noted that the use of words such as "first" and "second" to define components is only for the convenience of distinguishing the corresponding components. If not otherwise stated, the above words have no special meaning and cannot be understood as limiting the scope of protection of this application. In addition, although the terms used in this application are selected from well-known and commonly used terms, some terms mentioned in the specification of this application may be selected by the applicant at his or her discretion, and their detailed meanings are explained in the relevant parts of the description of this article. In addition, it is required to understand this application not only by the actual terms used, but also by the meaning implied by each term.

Claims

1. A method for developing a heat pipe reactor system analysis program, characterized in that: include: Determine the application scope of the system analysis program, identify the phenomena that need to be simulated within the application scope, classify the phenomena according to their importance, and obtain a phenomenon identification and ranking table; Determining functional requirements of the system analysis program based on the phenomenon identification and ranking table; Establish theoretical models of the core, heat pipe and heat exchanger respectively according to the functional requirements and performance requirements, wherein the performance requirements include calculation efficiency requirements and calculation stability requirements; The detailed design of the system analysis program is carried out according to the theoretical model to obtain the system analysis program, including: Designing the system analysis program architecture according to the theoretical model, the system architecture comprising a main program module, an input module, an output module, a physical property module, a system module and a numerical solution module, wherein the system module comprises a core calculation module, a heat pipe calculation module and a heat exchanger calculation module; A programming language is used to develop and program each module in the architecture.

2. The development method according to claim 1, characterized in that: The functional requirements of the system analysis program determined according to the phenomenon identification and ranking table include: The system analysis program should be able to best or conservatively simulate the phenomena ranked "high" in the phenomenon identification and ranking table, reasonably simulate the phenomena ranked "medium" in the phenomenon identification and ranking table, and simulate the phenomena ranked "low" in the phenomenon identification and ranking table.

3. The development method according to claim 1, characterized in that: The theoretical model of the core includes a core thermal model, a core physical calculation model and a core mechanical calculation model.

4. The development method according to claim 3, characterized in that: Establishing the core thermal model according to the calculation efficiency requirement includes: equating the heat pipe and the surrounding fuel rods into one channel, expanding it to the whole stack by connecting multiple channels in parallel, and establishing the core thermal model.

5. The development method according to claim 4, characterized in that: The channel is a regular polygon, and the core is composed of a plurality of regular polygons closely arranged in a honeycomb form.

6. The development method according to claim 3, characterized in that: Establishing the core physics calculation model according to the calculation efficiency requirement includes: using a point reactor neutron kinetic model as the core physics calculation model.

7. The development method according to claim 3, characterized in that: Establishing a theoretical model of the heat pipe according to the calculation stability requirement includes: establishing the theoretical model of the heat pipe using a multi-scale coupling method combining transient and steady states.

8. The development method according to claim 3, characterized in that: The core calculation module includes a core physics calculation module, a core thermal calculation module, and a core mechanics calculation module.

9. The development method according to claim 8, characterized in that: The core physics calculation module includes a point reactor neutron dynamics calculation module, a reactivity feedback module and a decay heat calculation module.

10. The development method according to claim 8, characterized in that: The core thermal engineering calculation module includes a fuel zone heat conduction calculation module, a cladding, a matrix and other heat conduction calculation modules, a heat transfer calculation module between adjacent channels and heat conduction calculation modules of other heat dissipation components.

11. The development method according to claim 1, characterized in that: Also includes: The heat pipe reactor system analysis program is tested and verified.

12. The development method according to claim 11, characterized in that: Testing and verification of the heat pipe reactor system analysis program includes: According to the functional requirements, a test matrix is ​​listed, wherein the test matrix includes a plurality of test cases; Determine whether the test matrix completely covers the phenomena in the phenomenon identification and ranking table, and if so, use the test matrix to verify the integrity of the program function.

13. The development method according to claim 11, characterized in that: The comparative data of the test cases in each test matrix include theoretical solutions, calculation results of other mature programs and experimental data.

14. The development method according to any one of claims 1 to 13, characterized in that: The application scope includes the scheme design, test pre-analysis and safety analysis of heat pipe reactors.

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