Safety analysis method and system for isotope irradiation production of high-temperature gas cooled reactor

Abstract

The invention provides a safety analysis method and system for isotope irradiation production of a high-temperature gas cooled reactor, and the method comprises the steps: building a reactor core model of a pebble-bed high-temperature gas cooled reactor and a target model of a selected target type based on a formulated target irradiation scheme; calculating reactor core states under various working conditions based on the reactor core model and the target model to obtain reactor core key parameters; judging whether the reactor core key parameters belong to a safety range or not, and under the condition that the reactor core key parameters belong to the safety range, performing accident development sequence calculation based on the reactor core key parameters to obtain a simulated accident result; judging whether the simulation accident result is enveloped by a safety accident in the final safety analysis report of the high-temperature gas cooled reactor or not, and obtaining a safety analysis result of isotope irradiation production of the high-temperature gas cooled reactor under the condition that the simulation accident result is enveloped by the safety accident in the final safety analysis report of the high-temperature gas cooled reactor. And how to carry out physical and thermal safety analysis of isotope irradiation production of the pebble-bed high-temperature gas cooled reactor is determined.

Description

Technical Field

[0001] The present application relates to the technical field of safety analysis of radioactive isotopes produced by reactor irradiation, and in particular to a safety analysis method and system for isotope irradiation production in a high-temperature gas-cooled reactor. Background Art

[0002] The pebble bed high temperature gas-cooled reactor uses spherical fuel elements such as Figure 1 As shown in the figure, the hemisphere after the fuel ball is cut includes an outer fuel-free area 11 and an inner fuel area 12. The fuel area 12 covers a plurality of fuel particles. The fuel particles include outer dense P y C layer 13, SiC layer 14, inner dense P y C layer 15, loose P y C Tier 16 and UO 2 The core structure of the pebble bed high temperature gas-cooled reactor can be simply described as a cylindrical pebble bed in the middle of the core with spherical fuel elements randomly stacked, and graphite internal components, carbon internal components, metal internal components, and pressure vessels outside the pebble bed. Figure 2 As shown, the graphite pile internal component includes a top reflection layer 21, a side reflection layer 22 and a bottom reflection layer 23. In the side reflection layer 22 of the graphite pile internal component, a control rod channel 31, an absorption ball channel 32, a cold helium channel 33, a neutron source channel 34, and a physical starting device channel 35 are arranged. Figure 3 shown.

[0003] When the pebble bed high temperature gas-cooled reactor reaches criticality for the first time, the neutron source channel and the physical start-up device channel (the two have the same structure and distribution circle diameter) are equipped with neutron sources and neutron counting tubes for physical start-up. During the operation of the reactor after criticality, the neutron source and the neutron counting tubes for physical start-up will be moved out of the side reflection layer, that is, the corresponding neutron source channel and physical start-up device channel are empty.

[0004] According to reactor physics calculations, the thermal neutron flux in the neutron source channel and the physical starter channel is considerable, comparable to the thermal neutron flux in the reactor core, such as Figure 4 As shown. Therefore, the above two channels can be completely used for isotope production through modification; for the newly built pebble bed high temperature gas-cooled reactor, isotope production can be considered in the side reflector layer in the design. In this way, through the production of isotopes, the pebble bed high temperature gas-cooled reactor nuclear power plant can generate more than 100 million yuan in new revenue each year, greatly improving the economic efficiency of the nuclear power plant.

[0005] The irradiation target of the isotope is a neutron absorber. During the process of loading, fixing and removing from the irradiation channel, the physical and thermal state of the reactor will change, which may affect the safe operation of the reactor. Therefore, the physical and thermal safety analysis and demonstration in the isotope production process is an indispensable and important link. Since the pebble bed high temperature gas-cooled reactor is a new type of reactor, there is currently no precedent for using this type of reactor to carry out isotope irradiation production, so there is no safety analysis method for isotope irradiation production in the pebble bed high temperature gas-cooled reactor. Summary of the invention

[0006] The present application aims to solve one of the technical problems in the related art at least to some extent.

[0007] To this end, the first purpose of this application is to propose a safety analysis method for high-temperature gas-cooled reactor isotope irradiation production, so as to realize the safety analysis of high-temperature gas-cooled reactor isotope irradiation production and solve the problem of lack of physical thermal safety analysis demonstration method in the isotope production process in related technologies.

[0008] The second objective of the present application is to provide a safety analysis system for high temperature gas-cooled reactor isotope irradiation production.

[0009] The third objective of the present application is to provide an electronic device.

[0010] A fourth objective of the present application is to provide a computer-readable storage medium.

[0011] A fifth object of the present application is to provide a computer program product.

[0012] To achieve the above-mentioned purpose, the first embodiment of the present application proposes a safety analysis method for high temperature gas-cooled reactor isotope irradiation production, comprising:

[0013] Based on the formulated target irradiation plan, the core model of the pebble bed high temperature gas-cooled reactor and the target model of the selected target type are established;

[0014] Based on the core model and the target model, the core states under various working conditions are calculated to obtain key core parameters;

[0015] determining whether the core key parameters are within a safe range, and if the core key parameters are within the safe range, performing accident development sequence calculation based on the core key parameters to obtain a simulated accident result;

[0016] Determine whether the simulated accident result is covered by the safety accidents in the final safety analysis report of the high temperature gas-cooled reactor, and obtain the safety analysis result of the isotope irradiation production of the high temperature gas-cooled reactor when the simulated accident result is covered by the safety accidents in the final safety analysis report of the high temperature gas-cooled reactor.

[0017] In some implementations, the method further includes:

[0018] When the core key parameters are not within the safety range, the target irradiation plan is re-formulated.

[0019] In some implementations, obtaining the safety analysis result of isotope irradiation production of a high temperature gas-cooled reactor based on whether the simulated accident result is included in the safety accident in the final safety analysis report of the high temperature gas-cooled reactor comprises:

[0020] When the simulated accident result is covered by the safety accident in the final safety analysis report of the high temperature gas-cooled reactor, it is determined that the target irradiation plan meets the safety requirements of the reactor.

[0021] In some implementations, obtaining the safety analysis result of isotope irradiation production of a high temperature gas-cooled reactor based on whether the simulated accident result is included in the safety accident in the final safety analysis report of the high temperature gas-cooled reactor further includes:

[0022] When the simulated accident result is not covered by the safety accident in the final safety analysis report of the high temperature gas-cooled reactor, the target irradiation plan is re-formulated.

[0023] In some implementations, establishing a core model of a pebble bed high temperature gas-cooled reactor and a target model of a selected target type includes:

[0024] The core model of the pebble bed high temperature gas-cooled reactor and the target model of the selected target type are established using the pebble bed high temperature gas-cooled reactor physical thermal calculation software and Monte Carlo software.

[0025] In some implementations, the performing of accident development sequence calculation based on the core key parameters to obtain a simulated accident result includes:

[0026] The core key parameters are input into the accident analysis program to calculate the accident development sequence and obtain the simulated accident results.

[0027] In some implementations, re-formulating the target irradiation plan includes:

[0028] The target loading amount in the target irradiation scheme is adjusted and the target structure in the target irradiation scheme is changed.

[0029] In some implementations, the multiple operating conditions include full power conditions, low power conditions, and subcritical conditions, and the core key parameters include core power distribution, temperature distribution, and gas pressure.

[0030] In some implementations, the target type is selected based on a neutron absorption property of the target material.

[0031] To achieve the above-mentioned purpose, the second embodiment of the present application proposes a safety analysis system for high temperature gas-cooled reactor isotope irradiation production, comprising:

[0032] A model building module is used to build a core model of a pebble bed high temperature gas-cooled reactor and a target model of a selected target type based on a formulated target irradiation plan;

[0033] A state calculation module, used to calculate the core state under various working conditions based on the core model and the target model, and obtain key core parameters;

[0034] An accident simulation module is used to determine whether the core key parameters are within a safe range, and if the core key parameters are within a safe range, calculate the accident development sequence based on the core key parameters to obtain a simulated accident result;

[0035] The accident comparison module is used to determine whether the simulated accident result is covered by the safety accident in the final safety analysis report of the high temperature gas-cooled reactor, and to obtain the safety analysis result of the isotope irradiation production of the high temperature gas-cooled reactor when the simulated accident result is covered by the safety accident in the final safety analysis report of the high temperature gas-cooled reactor.

[0036] In some implementations, the system includes a regimen adjustment module configured to:

[0037] When the core key parameters are not within the safety range, the target irradiation plan is re-formulated.

[0038] In some implementations, the accident comparison module is specifically used to:

[0039] In the case that the simulated accident result is covered by the safety accident in the final safety analysis report of the high temperature gas-cooled reactor, it is determined that the target irradiation plan meets the safety requirements of the reactor.

[0040] In some implementations, the scheme adjustment module is further configured to:

[0041] When the simulated accident result is not covered by the safety accident in the final safety analysis report of the high temperature gas-cooled reactor, the target irradiation plan is re-formulated.

[0042] In some implementations, the model building module is specifically configured to:

[0043] The core model of the pebble bed high temperature gas-cooled reactor and the target model of the selected target type are established using the pebble bed high temperature gas-cooled reactor physical thermal calculation software and Monte Carlo software.

[0044] In some implementations, when the accident simulation module calculates the accident development sequence based on the core key parameters to obtain the simulated accident result, it is used to:

[0045] The core key parameters are input into the accident analysis program to calculate the accident development sequence and obtain the simulated accident results.

[0046] In some implementations, when re-formulating the target irradiation plan, the plan adjustment module is used to:

[0047] The target loading amount in the target irradiation scheme is adjusted and the target structure in the target irradiation scheme is changed.

[0048] In some implementations, the multiple operating conditions include full power conditions, low power conditions, and subcritical conditions, and the core key parameters include core power distribution, temperature distribution, and gas pressure.

[0049] In some implementations, the target type is selected based on a neutron absorption property of the target material.

[0050] To achieve the above-mentioned purpose, the third aspect embodiment of the present application proposes an electronic device, comprising: a processor, and a memory communicatively connected to the processor; the memory stores computer-executable instructions; the processor executes the computer-executable instructions stored in the memory to implement the method described in the first aspect.

[0051] To achieve the above-mentioned purpose, the fourth aspect of the present application proposes a computer-readable storage medium, in which computer-readable storage medium is stored computer-executable instructions, and when the computer-executable instructions are executed by a processor, they are used to implement the method described in the first aspect.

[0052] To achieve the above-mentioned purpose, the fifth aspect of the present application proposes a computer program product, including a computer program, which implements the method described in the first aspect when executed by a processor.

[0053] The safety analysis method, device, electronic equipment and storage medium for isotope irradiation production in a high-temperature gas-cooled reactor provided in the present application construct a core model and a target model of a pebble-bed type high-temperature gas-cooled reactor based on a formulated isotope target irradiation plan, calculate the core state under various working conditions based on the model, and perform safety evaluation and accident simulation of the target irradiation plan based on the calculation results, and finally complete the physical thermal safety analysis demonstration of the present invention by comparing the final safety analysis report of the reactor; clarify how to carry out the physical thermal safety analysis of isotope irradiation production in a pebble-bed type high-temperature gas-cooled reactor, and provide compliance and reference for risk determination, program selection, model establishment, safety assessment, and formulation of response measures related to subsequent physical thermal safety analysis demonstration of high-temperature reactor isotope production.

[0054] Additional aspects and advantages of the present application will be given in part in the description below, and in part will become apparent from the description below, or will be learned through the practice of the present application. BRIEF DESCRIPTION OF THE DRAWINGS

[0055] The above and / or additional aspects and advantages of the present application will become apparent and easily understood from the following description of the embodiments in conjunction with the accompanying drawings, in which:

[0056] Figure 1 A schematic diagram of the structure of a pebble bed high temperature gas-cooled reactor fuel element provided as an example of this application;

[0057] Figure 2 A schematic diagram of the core structure of a pebble bed high temperature gas-cooled reactor provided as an example of this application;

[0058] Figure 3 A schematic diagram of the pore structure of the side reflector layer of a pebble bed high temperature gas-cooled reactor provided as an example of the present application;

[0059] Figure 4 A thermal neutron flux distribution diagram of a core of a pebble bed high temperature gas-cooled reactor provided as an example of the present application;

[0060] Figure 5 A schematic flow chart of a safety analysis method for high temperature gas-cooled reactor isotope irradiation production provided in an embodiment of the present application;

[0061] Figure 6 A block diagram of a safety analysis system for high temperature gas-cooled reactor isotope irradiation production provided in an embodiment of the present application;

[0062] Figure 7 A block diagram of an electronic device provided in an embodiment of the present application. DETAILED DESCRIPTION

[0063] Embodiments of the present application are described in detail below, and examples of the embodiments are shown in the accompanying drawings, wherein the same or similar reference numerals throughout represent the same or similar elements or elements having the same or similar functions. The embodiments described below with reference to the accompanying drawings are exemplary and are intended to be used to explain the present application, and should not be construed as limiting the present application.

[0064] The following describes the safety analysis method, device and equipment for high temperature gas-cooled reactor isotope irradiation production according to an embodiment of the present application with reference to the accompanying drawings.

[0065] Figure 5 A schematic flow chart of a safety analysis method for high temperature gas-cooled reactor isotope irradiation production provided in an embodiment of the present application.

[0066] It should be noted that the executor of the safety analysis method for high-temperature gas-cooled reactor isotope irradiation production of the embodiment of the present application is the safety analysis system for high-temperature gas-cooled reactor isotope irradiation production of the embodiment of the present application, and the safety analysis system for high-temperature gas-cooled reactor isotope irradiation production can be configured in an electronic device so that the electronic device can perform the safety analysis function for high-temperature gas-cooled reactor isotope irradiation production.

[0067] like Figure 5 As shown, the safety analysis method for high temperature gas-cooled reactor isotope irradiation production includes the following steps:

[0068] Step S101, based on the formulated target irradiation plan, a core model of a pebble bed high temperature gas-cooled reactor and a target model of a selected target type are established.

[0069] It should be noted that when formulating a target irradiation plan, it is necessary to select the target type.

[0070] In some embodiments, the target type is selected based on factors including the neutron absorption properties of the target material.

[0071] For example, during the design stage of the target irradiation plan for a pebble bed high temperature gas-cooled reactor isotope (not just one isotope, there may be multiple isotopes to choose from), suitable targets (such as targets with the largest neutron absorption cross-section and targets with the smallest neutron absorption cross-section) are selected for analysis based on the neutron absorption characteristics of different target materials, so that the analysis results can cover various possible irradiation targets, thereby selecting suitable targets.

[0072] In some embodiments, a method for establishing a core model of a pebble bed high temperature gas-cooled reactor and a target model of a selected target type includes: using pebble bed high temperature gas-cooled reactor physical thermal calculation software and Monte Carlo software to establish a core model of a pebble bed high temperature gas-cooled reactor and a target model of a selected target type.

[0073] For example, the VSOP software can be selected as the physical thermal calculation software for the pebble bed high temperature gas-cooled reactor, and the MCNP software can be selected as the Monte Carlo software.

[0074] Step S102, based on the core model and the target model, the core states under various working conditions are calculated to obtain key core parameters.

[0075] Exemplarily, the various operating conditions may include but are not limited to full power conditions, low power conditions and subcritical conditions, and the key core parameters may include but are not limited to core power distribution, temperature distribution and gas pressure.

[0076] This step calculates the core state under typical operating conditions (full power, low power, subcritical) based on the established core model and target model, and obtains key core parameters such as core power distribution, temperature distribution, and gas pressure, providing basic data for subsequent steps.

[0077] Step S103, determining whether the core key parameters are within the safe range, and if the core key parameters are within the safe range, performing accident development sequence calculation based on the core key parameters to obtain simulated accident results.

[0078] It should be noted that after completing the core state calculation, the present invention performs a safety evaluation, that is, determines whether the key parameters of the core are within the safe range. When the key parameters of the core are within the safe range, the next step of accident safety analysis is performed, that is, the accident development sequence is calculated based on the key parameters of the core.

[0079] In some embodiments, a method for calculating an accident development sequence based on core key parameters to obtain simulated accident results includes: inputting core key parameters into an accident analysis program to calculate an accident development sequence to obtain simulated accident results.

[0080] Exemplarily, the calculation results of the core state calculation are input into the accident analysis program TINTE to perform accident development sequence calculations to simulate the changes in core parameters during an accident, such as core power density, fuel element temperature, pressure and other key physical and thermal parameters, to obtain simulated accident results.

[0081] In some embodiments, this step also includes: when the key core parameters are not within the safety range, re-formulating the target irradiation plan, and returning to step S101, based on the re-formulated target irradiation plan, establishing the core model of the pebble bed high temperature gas-cooled reactor and the target model of the selected target type.

[0082] That is to say, when the key core parameters are not within the safe range, new countermeasures need to be formulated, such as adjusting the target loading or changing the target structure to redesign the target irradiation plan and return to step S101 for execution.

[0083] Exemplarily, reformulating the target irradiation plan may include, but is not limited to: adjusting the target loading amount in the target irradiation plan and changing the target structure in the target irradiation plan.

[0084] Step S104, determining whether the simulated accident result is included in the safety accident in the final safety analysis report of the high temperature gas-cooled reactor, and obtaining the safety analysis result of the isotope irradiation production of the high temperature gas-cooled reactor when the simulated accident result is included in the safety accident in the final safety analysis report of the high temperature gas-cooled reactor.

[0085] In the case where the simulated accident results are covered by the safety accidents in the final safety analysis report of the high temperature gas-cooled reactor, the target irradiation plan can be determined to meet the safety requirements of the reactor, thus completing the physical thermal safety analysis demonstration of the present invention.

[0086] In some embodiments, this step also includes: when the simulated accident results are not covered by the safety accidents in the final safety analysis report of the high temperature gas-cooled reactor, it can be determined that the target irradiation plan does not meet the safety requirements of the reactor, and a new target irradiation plan needs to be re-formulated, and return to step S101, based on the re-formulated target irradiation plan, establish the core model of the pebble bed high temperature gas-cooled reactor and the target model of the selected target type.

[0087] For example, the simulated accident results are compared with the accidents in the final safety analysis report (FSAR) of the high temperature gas-cooled reactor to analyze whether the target irradiation process can be covered by the original safety analysis report. If the simulated accident results can be covered by the safety accidents in the FSAR, it means that the target irradiation plan meets the safety requirements of the reactor. If not, it means that the target irradiation plan is not feasible and needs to be readjusted.

[0088] The present invention comprehensively considers the design characteristics, system settings, design procedures, isotope irradiation scheme, etc. of the pebble bed type high temperature gas-cooled reactor, and for the first time formulates a safety analysis method for isotope irradiation production of the pebble bed type high temperature gas-cooled reactor.

[0089] The safety analysis method for isotope irradiation production in a high-temperature gas-cooled reactor of the embodiment of the present application is based on a formulated isotope target irradiation plan, constructs a core model and a target model of a pebble-bed type high-temperature gas-cooled reactor, calculates the core state under various working conditions based on the model, and performs safety evaluation and accident simulation of the target irradiation plan based on the calculation results, and finally completes the physical thermal safety analysis demonstration of the present invention by comparing the final safety analysis report of the reactor; clarifies how to carry out the physical thermal safety analysis of isotope irradiation production in a pebble-bed type high-temperature gas-cooled reactor, and provides compliance and reference for risk determination, program selection, model establishment, safety assessment, and formulation of response measures related to subsequent physical thermal safety analysis demonstration of high-temperature reactor isotope production.

[0090] In order to implement the above-mentioned embodiment, the present application also proposes a safety analysis system for high temperature gas-cooled reactor isotope irradiation production. Figure 6 This is a block diagram of a safety analysis system for high temperature gas-cooled reactor isotope irradiation production provided in an embodiment of the present application. Figure 6 As shown, the safety analysis system for high temperature gas-cooled reactor isotope irradiation production may include: a model building module 201 , a state calculation module 202 , an accident simulation module 203 and an accident comparison module 204 .

[0091] The model building module 201 is used to build a core model of a pebble bed high temperature gas-cooled reactor and a target model of a selected target type based on a formulated target irradiation plan;

[0092] A state calculation module 202 is used to calculate the core state under various working conditions based on the core model and the target model to obtain the key parameters of the core;

[0093] The accident simulation module 203 is used to determine whether the core key parameters are within the safe range, and if the core key parameters are within the safe range, calculate the accident development sequence based on the core key parameters to obtain the simulated accident results;

[0094] The accident comparison module 204 is used to determine whether the simulated accident result is included in the safety accident in the final safety analysis report of the high temperature gas-cooled reactor, and to obtain the safety analysis result of the isotope irradiation production of the high temperature gas-cooled reactor when the simulated accident result is included in the safety accident in the final safety analysis report of the high temperature gas-cooled reactor.

[0095] In some implementations, the system includes a scheme adjustment module 205 for:

[0096] When the key core parameters are not within the safe range, the target irradiation plan should be re-formulated.

[0097] In some implementations, the accident comparison module 204 is specifically configured to:

[0098] When the simulated accident results were covered by the safety accidents in the final safety analysis report of the high temperature gas-cooled reactor, it was determined that the target irradiation plan met the safety requirements of the reactor.

[0099] In some implementations, the solution adjustment module 205 is further configured to:

[0100] Under the circumstance that the simulated accident results are not covered by the safety accidents in the final safety analysis report of the high temperature gas-cooled reactor, the target irradiation plan is re-formulated.

[0101] In some implementations, the model building module 201 is specifically configured to:

[0102] The core model of the pebble bed high temperature gas-cooled reactor and the target model of the selected target type are established using the pebble bed high temperature gas-cooled reactor physical thermal calculation software and Monte Carlo software.

[0103] In some implementations, when the accident simulation module 203 calculates the accident development sequence based on the core key parameters and obtains the simulated accident result, it is used to:

[0104] The key core parameters are input into the accident analysis program to calculate the accident development sequence and obtain the simulated accident results.

[0105] In some implementations, when re-formulating the target irradiation plan, the plan adjustment module 205 is used to:

[0106] Adjust the target loading amount in the target irradiation plan and change the target structure in the target irradiation plan.

[0107] In some implementations, the multiple operating conditions include full power conditions, low power conditions, and subcritical conditions, and the key core parameters include core power distribution, temperature distribution, and gas pressure.

[0108] In some implementations, the target type is selected based on factors including the neutron absorption properties of the target material.

[0109] It should be noted that the aforementioned explanation of the embodiment of the safety analysis method for high temperature gas-cooled reactor isotope irradiation production is also applicable to the safety analysis system for high temperature gas-cooled reactor isotope irradiation production of this embodiment, and will not be repeated here.

[0110] In order to implement the above embodiment, the present application also proposes an electronic device. Figure 7 , Figure 7 is a block diagram of an electronic device provided in an embodiment of the present application. Figure 7 As shown, the electronic device 700 includes: a processor 701, and a memory 702 communicatively connected to the processor 701; the memory 702 stores computer-executable instructions; the processor 701 executes the computer-executable instructions stored in the memory to implement the method provided in the aforementioned embodiment.

[0111] In order to implement the above embodiments, the present application also proposes a computer-readable storage medium, in which computer-executable instructions are stored. When the computer-executable instructions are executed by a processor, they are used to implement the methods provided by the above embodiments.

[0112] In order to implement the above embodiments, the present application also proposes a computer program product, including a computer program, which implements the methods provided by the above embodiments when executed by a processor.

[0113] The collection, storage, use, processing, transmission, provision and disclosure of user personal information involved in this application are in compliance with relevant laws and regulations and do not violate public order and good morals.

[0114] It should be noted that personal information from users should be collected for legitimate and reasonable purposes and should not be shared or sold outside of these legitimate uses. In addition, such collection / sharing should be carried out after receiving the user's informed consent, including but not limited to notifying the user to read the user agreement / user notice and sign the agreement / authorization including authorization of relevant user information before the user uses the function. In addition, any necessary steps should be taken to protect and safeguard access to such personal information data and ensure that others who have access to personal information data comply with its privacy policy and procedures.

[0115] The present application is expected to provide an implementation scheme for users to selectively block the use or access of personal information data. That is, the present disclosure is expected to provide hardware and / or software to prevent or block access to such personal information data. Once the personal information data is no longer needed, the risk can be minimized by limiting data collection and deleting the data. In addition, when applicable, such personal information is de-identified to protect the privacy of the user.

[0116] In the description of the aforementioned embodiments, the description with reference to the terms "one embodiment", "some embodiments", "example", "specific example", or "some examples" etc. means that the specific features, structures, materials or characteristics described in conjunction with the embodiment or example are included in at least one embodiment or example of the present application. In this specification, the schematic representations of the above terms do not necessarily refer to the same embodiment or example. Moreover, the specific features, structures, materials or characteristics described may be combined in any one or more embodiments or examples in a suitable manner. In addition, those skilled in the art may combine and combine the different embodiments or examples described in this specification and the features of the different embodiments or examples, without contradiction.

[0117] In addition, the terms "first" and "second" are used for descriptive purposes only and should not be understood as indicating or implying relative importance or implicitly indicating the number of the indicated technical features. Therefore, the features defined as "first" and "second" may explicitly or implicitly include at least one of the features. In the description of this application, the meaning of "plurality" is at least two, such as two, three, etc., unless otherwise clearly and specifically defined.

[0118] Any process or method description in a flowchart or otherwise described herein may be understood to represent a module, fragment or portion of code comprising one or more executable instructions for implementing the steps of a custom logical function or process, and the scope of the preferred embodiments of the present application includes alternative implementations in which functions may not be performed in the order shown or discussed, including performing functions in a substantially simultaneous manner or in the reverse order depending on the functions involved, which should be understood by technicians in the technical field to which the embodiments of the present application belong.

[0119] The logic and / or steps represented in the flowchart or otherwise described herein, for example, can be considered as an ordered list of executable instructions for implementing logical functions, and can be embodied in any computer-readable medium for use by an instruction execution system, device or apparatus (such as a computer-based system, a system including a processor, or other system that can fetch instructions from an instruction execution system, device or apparatus and execute the instructions), or in combination with these instruction execution systems, devices or apparatuses. For the purpose of this specification, "computer-readable medium" can be any device that can contain, store, communicate, propagate or transmit a program for use by an instruction execution system, device or apparatus, or in combination with these instruction execution systems, devices or apparatuses. More specific examples of computer-readable media (a non-exhaustive list) include the following: an electrical connection with one or more wires (electronic device), a portable computer disk box (magnetic device), a random access memory (RAM), a read-only memory (ROM), an erasable and programmable read-only memory (EPROM or flash memory), a fiber optic device, and a portable compact disk read-only memory (CDROM). In addition, the computer-readable medium may even be paper or other suitable medium on which the program is printed, since the program may be obtained electronically, for example, by optically scanning the paper or other medium and then editing, interpreting or processing in other suitable ways if necessary, and then stored in a computer memory.

[0120] It should be understood that the various parts of the present application can be implemented by hardware, software, firmware or a combination thereof. In the above-mentioned embodiments, multiple steps or methods can be implemented by software or firmware stored in a memory and executed by a suitable instruction execution system. For example, if implemented by hardware, as in another embodiment, it can be implemented by any one of the following technologies known in the art or their combination: a discrete logic circuit having a logic gate circuit for implementing a logic function for a data signal, a dedicated integrated circuit having a suitable combination of logic gate circuits, a programmable gate array (PGA), a field programmable gate array (FPGA), etc.

[0121] A person skilled in the art may understand that all or part of the steps in the method for implementing the above-mentioned embodiment may be completed by instructing related hardware through a program, and the program may be stored in a computer-readable storage medium, which, when executed, includes one or a combination of the steps of the method embodiment.

[0122] In addition, each functional unit in each embodiment of the present application may be integrated into a processing module, or each unit may exist physically separately, or two or more units may be integrated into one module. The above-mentioned integrated module may be implemented in the form of hardware or in the form of a software functional module. If the integrated module is implemented in the form of a software functional module and sold or used as an independent product, it may also be stored in a computer-readable storage medium.

[0123] The storage medium mentioned above may be a read-only memory, a magnetic disk or an optical disk, etc. Although the embodiments of the present application have been shown and described above, it can be understood that the above embodiments are exemplary and cannot be understood as limiting the present application. A person of ordinary skill in the art may change, modify, replace and modify the above embodiments within the scope of the present application.

Claims

1. A safety analysis method for high temperature gas-cooled reactor isotope irradiation production, characterized in that: The following steps are involved: Based on the formulated target irradiation plan, the core model of the pebble bed high temperature gas-cooled reactor and the target model of the selected target type are established; Based on the core model and the target model, the core states under various working conditions are calculated to obtain key core parameters; determining whether the core key parameters are within a safe range, and if the core key parameters are within the safe range, performing accident development sequence calculation based on the core key parameters to obtain a simulated accident result; Determine whether the simulated accident result is covered by the safety accidents in the final safety analysis report of the high temperature gas-cooled reactor, and obtain the safety analysis result of the isotope irradiation production of the high temperature gas-cooled reactor when the simulated accident result is covered by the safety accidents in the final safety analysis report of the high temperature gas-cooled reactor.

2. The method according to claim 1, characterized in that The method further comprises: When the core key parameters are not within the safety range, the target irradiation plan is re-formulated.

3. The method according to claim 1, characterized in that The step of obtaining the safety analysis result of the high temperature gas-cooled reactor isotope irradiation production based on whether the simulated accident result is included in the safety accident in the final safety analysis report of the high temperature gas-cooled reactor comprises: In the case that the simulated accident result is covered by the safety accident in the final safety analysis report of the high temperature gas-cooled reactor, it is determined that the target irradiation plan meets the safety requirements of the reactor.

4. The method according to claim 3, characterized in that The step of obtaining the safety analysis result of the high temperature gas-cooled reactor isotope irradiation production based on whether the simulated accident result is included in the safety accident in the final safety analysis report of the high temperature gas-cooled reactor includes: When the simulated accident result is not covered by the safety accident in the final safety analysis report of the high temperature gas-cooled reactor, the target irradiation plan is re-formulated.

5. The method according to claim 1, characterized in that The method of establishing a core model of a pebble bed high temperature gas-cooled reactor and a target model of a selected target type comprises: The core model of the pebble bed high temperature gas-cooled reactor and the target model of the selected target type are established using the pebble bed high temperature gas-cooled reactor physical thermal calculation software and Monte Carlo software.

6. The method according to claim 1, characterized in that The calculation of the accident development sequence based on the core key parameters to obtain the simulated accident result comprises: The core key parameters are input into the accident analysis program to calculate the accident development sequence and obtain the simulated accident results.

7. The method according to claim 2 or 4, characterized in that: The re-formulating the target irradiation plan includes: The target loading amount in the target irradiation scheme is adjusted and the target structure in the target irradiation scheme is changed.

8. The method according to claim 1, characterized in that The multiple operating conditions include full power operating condition, low power operating condition and subcritical operating condition, and the core key parameters include core power distribution, temperature distribution and gas pressure.

9. The method according to claim 1, characterized in that: The target type is selected based on the neutron absorption characteristics of the target material.

10. A safety analysis system for high temperature gas-cooled reactor isotope irradiation production, characterized in that: include: A model building module is used to build a core model of a pebble bed high temperature gas-cooled reactor and a target model of a selected target type based on a formulated target irradiation plan; A state calculation module, used to calculate the core state under various working conditions based on the core model and the target model, and obtain key core parameters; An accident simulation module is used to determine whether the core key parameters are within a safe range, and if the core key parameters are within a safe range, calculate the accident development sequence based on the core key parameters to obtain a simulated accident result; The accident comparison module is used to determine whether the simulated accident result is covered by the safety accident in the final safety analysis report of the high temperature gas-cooled reactor, and to obtain the safety analysis result of the isotope irradiation production of the high temperature gas-cooled reactor when the simulated accident result is covered by the safety accident in the final safety analysis report of the high temperature gas-cooled reactor.

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