A method and device for analyzing the core bypass flow sensitivity of a pebble bed high temperature gas cooled reactor

Abstract

The application discloses a kind of pebble bed high temperature gas cooled reactor core side flow sensitivity analysis method and device, it is related to nuclear reactor physical thermal design technical field, wherein the method includes: the physical thermal coupling calculation model that can reflect pebble bed high temperature gas cooled reactor core geometry, material and flow channel characteristics is established, the flow characteristics of main flow and side flow channel are distinguished;Then determine the reactor design parameter, set analysis interval and typical working condition with side flow share as variable, distribute main flow and side flow flow according to total flow conservation;Steady coupling calculation is carried out to each working condition, and corresponding thermal data is obtained after convergence;The sensitivity of target thermal parameter to side flow share is analyzed, the upper limit of side flow share is determined under the condition of meeting safety limit and performance index, and the quantitative determination of side flow share limit is completed.The application realizes the quantitative evaluation of side flow influence by fine coupling calculation and sensitivity analysis, solves the problem that traditional design relies on experience and risk is difficult to predict.

Description

Technical Field

[0001] This invention relates to the field of nuclear reactor physics and thermal design technology, and in particular to a method and apparatus for analyzing the bypass sensitivity of a pebble bed type high-temperature gas-cooled reactor core. Background Technology

[0002] The pebble bed high-temperature gas-cooled reactor (HTR-PM) is a typical example of this technology. It is an advanced reactor type possessing characteristics of fourth-generation nuclear power, boasting advantages such as high core outlet temperature, excellent inherent safety, passive residual heat removal, modular construction, high power generation efficiency, wide range of applications, and low radioactive waste generation. Leveraging its strong inherent safety and multi-purpose application potential, the pebble bed HTR-PM can not only be used for large-scale clean power generation but also support important scenarios such as high-temperature hydrogen production, industrial process heating, steel smelting, and urban district heating. It represents a key technological route for achieving deep nuclear energy substitution for fossil fuels and promoting low-carbon transformation in the industrial sector.

[0003] The core of a pebble-bed high-temperature gas-cooled reactor primarily utilizes ceramic-based graphite and carbonaceous internal components, assembled from numerous graphite and carbon bricks. Structurally, this forms main cooling channels for mainstream cooling, including cold helium rising channels, control rod channels, and absorber ball shutdown channels. Simultaneously, various bypass channels are formed at brick joints and component assembly gaps, such as graphite brick gaps, unloading pipe gaps, and control rod channel gaps. The total primary coolant flow through the core consists of the mainstream flow responsible for effective cooling and the bypass flow through the bypass paths. The bypass share, representing the proportion of bypass flow to the total coolant flow, directly determines the effective cooling flow of the core and is a core factor influencing key performance and safety parameters such as core power level, coolant outlet temperature, and structural material temperature.

[0004] my country's high-temperature gas-cooled reactor (HTR-PM) nuclear power plant demonstration project has a designed rated thermal power of 250MW and a core outlet helium temperature target of 750℃ to meet the requirements of high-temperature process heat applications. Actual operating data shows that, due to objectively existing bypass channels such as assembly gaps and structural clearances within the reactor components, the actual bypass share is significantly higher than the design expectation, reaching 35%–45% in measured measurements. This excessively high bypass share directly leads to insufficient effective core cooling flow. When the reactor thermal power is increased to approximately 200MW, the primary loop outlet helium temperature only reaches about 570℃, far below the design target of 750℃. Simultaneously, the temperature of graphite structural components exceeds the design value by about 22%, adversely affecting reactor performance and structural safety.

[0005] High-temperature outlet temperature is a core technical characteristic that distinguishes pebble bed high-temperature gas-cooled reactors from traditional reactor types, enabling high-end applications such as nuclear hydrogen production, industrial high-temperature heating, and nuclear steelmaking. If the outlet temperature fails to meet design requirements, its multi-purpose and high-efficiency advantages will be difficult to realize, severely restricting the engineering promotion and industrial application of this reactor type. Currently, in the design phase of pebble bed high-temperature gas-cooled reactors, the impact assessment of bypass channels and bypass fractions largely relies on empirical assumptions or simplified analytical models, lacking a systematic and refined bypass sensitivity analysis method. This makes it difficult to accurately quantify the response laws of core thermal-hydraulic, power distribution, and temperature field under different bypass fractions, failing to provide a reliable basis for determining bypass fraction limits and optimizing the reactor internal structure. This can easily lead to deviations between reactor design and actual operation, and even potential safety risks. Therefore, it is urgent to establish a precise and systematic bypass sensitivity analysis method for pebble bed high-temperature gas-cooled reactor cores to support core structure optimization design, effective control of bypass fractions, and ensure safe, efficient, and design-performance-target reactor operation. Summary of the Invention

[0006] The main objective of this invention is to provide a method for analyzing the bypass sensitivity of a pebble bed type high-temperature gas-cooled reactor core.

[0007] Another objective of this invention is to provide a pebble bed type high-temperature gas-cooled reactor core bypass sensitivity analysis device.

[0008] The third objective of this invention is to provide an electronic device.

[0009] A fourth objective of this invention is to provide a non-transitory computer-readable storage medium.

[0010] To achieve the above objectives, a first aspect of the present invention provides a method for analyzing the bypass sensitivity of a pebble bed type high-temperature gas-cooled reactor core, comprising:

[0011] A physical-thermal-engineering coupled calculation model is established to reflect the geometry and material arrangement of the core of a pebble bed type high-temperature gas-cooled reactor. The physical-thermal-engineering coupled calculation model is used to distinguish and characterize the flow area and flow resistance characteristics of the main flow channel and various bypass channels. The design target parameters of the pebble bed high-temperature gas-cooled reactor are determined, the bypass flow share is used as the target analysis variable, the analysis range of the bypass flow share and multiple bypass flow share values ​​are set, and the flow is allocated between the main flow channel and the bypass flow channel based on the total flow conservation. Based on the physical-thermal coupling calculation model, corresponding flow distribution boundary conditions are applied to each bypass share value, and core steady-state physical-thermal coupling calculations are carried out until the power distribution, temperature field and flow distribution reach a convergent state, and thermal calculation data under each bypass share condition are obtained. Based on the thermal calculation data under each bypass share condition, the sensitivity of the target thermal parameters to the bypass share is analyzed. Under the premise of meeting the design safety limit and design performance target, the allowable upper limit of the bypass share is determined, thus realizing the determination of the bypass share limit of the pebble bed high-temperature gas-cooled reactor.

[0012] Optionally, a physical-thermal-engineering coupled calculation model reflecting the core geometry and material arrangement of a pebble bed type high-temperature gas-cooled reactor is established, including: Collect and input the core geometry parameters, material arrangement parameters, fuel element characteristic parameters, and primary loop system design parameters of the pebble bed high-temperature gas reactor; Select and employ validated nuclear reactor system analysis programs or combinations thereof to construct a refined computational model capable of simulating the multi-physics coupling behavior of neutronics, thermal-hydraulic, and fuel performance within the reactor core.

[0013] Optionally, the design target parameters of the pebble bed high-temperature gas-cooled reactor are determined, with the bypass flow fraction as the target analysis variable. The analysis range of the bypass flow fraction and multiple bypass flow fraction values ​​are set, and the flow is allocated between the main flow channel and the bypass flow channel based on the total flow conservation, including: Determine and input the design target parameters for the reactor rated thermal power, primary coolant inlet temperature, target coolant outlet temperature, and primary total mass flow rate; The sidestream share is defined as the target analysis variable, and the sidestream share is defined as the ratio of sidestream flow to total flow. Based on engineering experience, reference data of similar reactor types, and conservative analysis principles, the sideflow share analysis range covering the design expected value to the maximum possible deviation value is determined and set, and a preset discrete sideflow share value is selected as the analysis condition. Based on the total flow conservation relationship, the main flow and the bypass flow are calculated and allocated for each discrete bypass share operating condition, forming the flow allocation boundary conditions for the corresponding operating condition.

[0014] Optionally, based on the physical-thermal coupling calculation model, corresponding flow distribution boundary conditions are applied to each bypass share value, and steady-state physical-thermal coupling calculations of the reactor core are performed until the power distribution, temperature field, and flow distribution reach a convergence state, obtaining thermal calculation data under each bypass share condition, including: Apply the flow distribution boundary conditions corresponding to each bypass share operating condition to the established physical-thermal-hydraulic coupling calculation model; The neutronics-thermal-hydraulic-fuel performance coupled calculation program was launched to simultaneously iteratively solve the core power distribution, coolant flow distribution, and temperature field of core and structural materials. The calculation is continuously iterated until the core power distribution, temperature field and flow distribution all meet the preset convergence criteria, and the steady-state thermal calculation data corresponding to each bypass flow share condition are output and stored.

[0015] Optionally, based on the thermal calculation data under each bypass flow share condition, analyze the sensitivity of the target thermal parameters to the bypass flow share, including: Extract the target safety and performance parameters of fuel element maximum temperature, fuel element average temperature, graphite reflector maximum temperature, coolant outlet temperature, and core power distribution from the calculation results of each operating condition; Using the bypass flow share as the independent variable and each target thermal parameter as the dependent variable, the variation law of the target parameters with the bypass flow share is fitted and analyzed. Calculate and determine the sensitivity coefficient of the target parameter to the bypass share. The sensitivity coefficient is expressed as the ratio of the change in the target parameter to the change in the bypass share. Identify and determine the target control parameter that is most significantly affected by the bypass.

[0016] Optionally, and provided that design safety limits and design performance objectives are met, an upper limit for the allowable bypass flow share may be determined, including: The calculation results of the target parameters under each bypass share operating condition are compared and constrained with the reactor design safety limits, material allowable temperature limits and design performance targets item by item. Under the constraint that all target parameters meet the design safety limits and basically achieve the design performance targets, the maximum allowable bypass flow share for this reactor type is determined through trend analysis and operating condition verification. The determined maximum bypass share is used as the upper limit and control target of the bypass share in the core design stage, and is used to provide feedback guidance for the design of in-core components, control of gap size, and optimization of primary loop total flow design.

[0017] To achieve the above objectives, a second aspect of the present invention provides a pebble bed type high-temperature gas-cooled reactor core bypass sensitivity analysis device, comprising: The model building module is used to establish a physical-thermal-engineering coupled calculation model that reflects the geometry and material arrangement of the core of the pebble bed type high-temperature gas-cooled reactor. The physical-thermal-engineering coupled calculation model is used to distinguish and characterize the flow area and flow resistance characteristics of the main flow channel and various bypass channels. The parameter setting module is used to determine the design target parameters of the pebble bed high-temperature gas-cooled reactor, with the bypass flow share as the target analysis variable, setting the analysis range of the bypass flow share and multiple bypass flow share values, and distributing the flow between the main flow channel and the bypass flow channel based on the total flow conservation. The coupling calculation module is used to apply corresponding flow distribution boundary conditions to each bypass share value based on the physical-thermal coupling calculation model, carry out core steady-state physical-thermal coupling calculation, until the power distribution, temperature field and flow distribution reach the convergence state, and obtain thermal calculation data under each bypass share condition. The limit determination module is used to analyze the sensitivity of the target thermal parameters to the bypass share based on the thermal calculation data under each bypass share condition, and determine the allowable upper limit of the bypass share under the premise of meeting the design safety limit and design performance target, so as to realize the determination of the bypass share limit of the pebble bed high temperature gas-cooled reactor.

[0018] Regarding the apparatus in the above embodiments, the specific manner in which each module performs its operation has been described in detail in the embodiments related to the method, and will not be elaborated upon here.

[0019] To achieve the above objectives, a third aspect of this application provides an electronic device, including a processor and a memory; wherein the processor reads executable program code stored in the memory to run a program corresponding to the executable program code, for implementing a pebble bed type high-temperature gas-cooled reactor core bypass sensitivity analysis method as described in the first aspect embodiment.

[0020] To achieve the above objectives, the fourth aspect of this application proposes a non-transitory computer-readable storage medium storing a computer program thereon, which, when executed by a processor, implements a pebble bed type high-temperature gas-cooled reactor core bypass sensitivity analysis method as described in the first aspect embodiment.

[0021] The embodiments of the present invention have the following beneficial effects: 1. This invention can systematically and quantitatively reveal the influence of bypass flow fraction on key thermal parameters of pebble bed high-temperature gas-cooled reactors. Through refined physical-thermal coupling calculations and sensitivity analysis, it replaces the traditional design method that relies on empirical assumptions and simplified estimations, significantly improving the accuracy and reliability of bypass flow impact assessment and providing quantitative support for core design.

[0022] 2. This invention can identify operational risks caused by excessive bypass flow in advance during the reactor design stage, effectively predict problems such as insufficient effective core cooling flow, low outlet temperature, and overheating of structural materials, and avoid situations where power and outlet temperature cannot meet design specifications, thereby reducing potential safety hazards in engineering implementation and later operation.

[0023] 3. This invention can quantitatively determine the upper limit of the allowable bypass flow share, providing a clear basis for bypass flow control objectives, optimization of in-core component assembly clearances, and primary loop flow design. It is beneficial to guide the refined design of the core structure, optimize the distribution of mainstream and bypass flow, and ensure that the pebble bed high-temperature gas-cooled reactor meets the requirements of high-temperature outlet temperature and long-term safe operation while operating at high power and high efficiency. Attached Figure Description

[0024] The above and / or additional aspects and advantages of the present invention will become apparent and readily understood from the following description of the embodiments taken in conjunction with the accompanying drawings, wherein: Figure 1 A flowchart of a sideflow sensitivity analysis method for a pebble bed type high-temperature gas-cooled reactor core provided by an embodiment of the present invention; Figure 2 A flowchart illustrating the overall technical solution steps provided in the embodiments of the present invention; Figure 3 This is an example diagram of the grid division scheme for a pebble bed type high-temperature reactor provided in an embodiment of the present invention; Figure 4 This is a schematic diagram of the material arrangement of the core and external area of ​​a pebble bed type high-temperature gas-cooled reactor provided in an embodiment of the present invention; Figure 5 This is a schematic diagram of the coupled computational convection grid provided in an embodiment of the present invention; Figure 6 The maximum fuel temperature distribution diagram for design scheme A under different bypass fractions provided in this embodiment of the invention; Figure 7 This is a structural diagram of a pebble bed type high-temperature gas-cooled reactor core bypass sensitivity analysis device provided in an embodiment of the present invention. Detailed Implementation

[0025] It should be noted that, unless otherwise specified, the embodiments and features described in the present invention can be combined with each other. The present invention will now be described in detail with reference to the accompanying drawings and embodiments.

[0026] To enable those skilled in the art to better understand the present invention, the technical solutions of the present invention will be clearly and completely described below with reference to the accompanying drawings of the embodiments of the present invention. Obviously, the described embodiments are only some embodiments of the present invention, and not all embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative effort should fall within the scope of protection of the present invention.

[0027] The following describes, with reference to the accompanying drawings, a method and apparatus for analyzing the bypass sensitivity of a pebble bed type high-temperature gas-cooled reactor core according to an embodiment of the present invention.

[0028] Example 1 This invention provides a method for analyzing the bypass sensitivity of a pebble bed type high-temperature gas-cooled reactor core. Figure 1 This is a schematic flowchart illustrating a method for analyzing the bypass sensitivity of a pebble bed type high-temperature gas-cooled reactor core, provided in an embodiment of the present invention. Figure 1 As shown, the method includes the following steps: Step S1: Establish a physical-thermal-engineering coupled calculation model that reflects the geometry and material arrangement of the core of the pebble bed type high-temperature gas-cooled reactor. The physical-thermal-engineering coupled calculation model is used to distinguish and characterize the flow area and flow resistance characteristics of the main flow channel and various bypass channels.

[0029] In this embodiment of the application, in order to ensure the accuracy and reliability of the subsequent sideflow sensitivity analysis and the determination of the sideflow share limit, the primary task is to construct a refined physical-thermal-engineering coupling calculation model that fits the actual core operating conditions. This model needs to comprehensively and accurately reflect the core characteristics of the target pebble bed high-temperature gas-cooled reactor, providing solid model support for the entire analysis process.

[0030] In this embodiment of the application, before constructing the above-mentioned physical-thermal-engineering coupling calculation model, it is necessary to systematically collect various basic design parameters of the target pebble bed high-temperature gas-cooled reactor. Specifically, these parameters include core geometric parameters, core material arrangement parameters, fuel element characteristic parameters, and primary loop system design parameters. Core geometric parameters cover the overall core dimensions, boundaries of each region, and distribution of flow channels. Core material arrangement parameters specify the specific arrangement and distribution range of various graphite components, fuel elements, and structural materials. Fuel element characteristic parameters include fuel type, size, thermal conductivity, and burnup characteristics. Primary loop system design parameters include key parameters such as coolant type, system pressure, and total flow design value. All of the above parameters must be collected strictly in accordance with the actual design documents and engineering specifications of the target reactor type to ensure the authenticity and completeness of the parameters.

[0031] After collecting various basic parameters, in this embodiment of the application, a nuclear reactor system analysis program or program combination that has been verified in engineering practice and has reliable calculation accuracy will be used to construct a refined calculation model that can accurately simulate the multi-physics coupling behavior inside the reactor core based on all collected parameters. The core advantage of this calculation model is that it can achieve refined zoning of the core flow channels, clearly distinguishing between the main flow channels and various bypass channels. The main flow channels mainly include channels that effectively cool the core, such as cold helium riser channels, control rod channels, and absorber ball channels. The bypass channels cover all non-effective cooling channels, such as graphite brick splicing gaps, unloading pipe and component gaps, and control rod channel gaps. At the same time, for each type of main flow channel and bypass channel, the corresponding flow area and flow resistance characteristic parameters will be independently set and assigned according to their actual geometric dimensions, structural form, and flow characteristics, so as to achieve differentiated and precise characterization of the flow behavior in the main flow region and the bypass region.

[0032] For characterizing the flow resistance properties, this application uses a mature engineering formula for single-channel flow resistance to quantify the pressure drop characteristics of each flow channel, specifically:

[0033] in, The total pressure drop in the flow channel. This is the frictional pressure drop along the flow path (generated by friction between the coolant and the flow channel wall). This is a localized form resistance pressure drop (caused by sudden changes in the flow channel cross-section, turns, and other local structural features). The pressure drop is caused by gravity (generated by changes in the potential energy of the coolant). The pressure drop is due to the flow acceleration (caused by changes in coolant flow rate).

[0034] By assigning parameters such as friction coefficient and local resistance coefficient to the main channel and various bypass channels to match their geometric characteristics, and substituting them into the above formula, the pressure drop characteristics of each channel are accurately calculated. This effectively avoids the calculation deviation caused by the fuzzy representation of the channel in the traditional simplified model, and provides a reliable and accurate model basis for the steady-state coupling calculation under different bypass share conditions.

[0035] Furthermore, in this embodiment of the application, in order to efficiently and systematically complete the construction process of the above-mentioned physical-thermal coupling calculation model, this application also specifically sets up a corresponding model construction module. As one of the core modules for implementing the method of this application, this module is mainly used to receive and process various input core design data, including the core geometry, materials, fuel and primary circuit system related parameters collected above, and then automatically complete the establishment of a refined physical-thermal coupling calculation model. At the same time, this module also has a model calling function, which can reuse the completed and verified calculation model, effectively ensuring the accuracy and standardization of model construction, significantly improving the efficiency of model construction, and reducing the workload of subsequent analysis processes.

[0036] Step S2: Determine the design target parameters of the pebble bed type high-temperature gas-cooled reactor, take the bypass flow share as the target analysis variable, set the analysis range of the bypass flow share and multiple bypass flow share values, and allocate the flow between the main flow channel and the bypass flow channel based on the total flow conservation.

[0037] In this embodiment, to conduct a systematic bypass sensitivity analysis, it is first necessary to define and lock in the core design and operation objectives of the target pebble bed high-temperature gas-cooled reactor based on the actual engineering requirements. These target parameters serve as the baseline constraints for the entire analysis process and specifically include key indicators such as the reactor's rated thermal power, the inlet temperature of the primary coolant, the expected target outlet temperature of the coolant, and the total mass flow rate set for the primary system. The values ​​of these parameters strictly adhere to the reactor's design specifications and engineering practice standards, which are the foundation for ensuring the reactor's safe, efficient, and design-target-achieved operation.

[0038] After clarifying the core design target parameters, this application defines the bypass flow share as the key research variable in this sensitivity analysis. The specific mathematical expression for the bypass flow share is the ratio of bypass flow rate to total coolant flow rate, i.e.:

[0039] in, For sideline share, This represents the total flow rate of the bypass channel. This represents the total flow rate of the coolant.

[0040] This variable directly reflects the proportion of bypass flow rate that does not participate in the effective cooling process within the reactor core to the total cooling flow rate. It is a core factor affecting the effective cooling capacity of the reactor core and, consequently, determining the key thermal-hydraulic parameters of the core. Based on engineering practice experience and the accumulation of actual operating data from similar advanced reactor types both domestically and internationally, and adhering to the engineering principle of conservative analysis, this application's embodiments determine and set the analysis range for the bypass flow share. This range needs to cover the bypass flow share value expected during the reactor design phase and extend to the maximum deviation value that may occur during engineering, forming a complete analysis interval.

[0041] To achieve a comprehensive quantitative analysis of the impact of bypass flow share, this embodiment scientifically selects multiple discrete bypass flow share values ​​as independent analysis conditions within a pre-defined bypass flow share analysis interval. These condition points must be representative, including both conventional conditions near the design expected value and extreme conditions with varying degrees of deviation, to ensure comprehensive coverage of the actual bypass flow share range that may occur in the project. For each selected bypass flow share value, this embodiment strictly adheres to the fundamental principle of total flow conservation in fluid mechanics, calculating and rationally allocating the flow rate of the main flow channel and the flow rates of various bypass channels, clarifying the specific flow allocation ratio between the main flow channel and each bypass channel under each condition, thereby forming standardized flow allocation boundary conditions suitable for each analysis condition.

[0042] The formula for the conservation of total flow is as follows:

[0043] in, The total traffic volume of the main channel.

[0044] By combining the definition of sidestream share, the flow distribution relationship between mainstream and sidestream can be directly obtained:

[0045] .

[0046] The entire parameter setting and boundary condition construction process described above is uniformly executed by the parameter setting module in this application. As an important component of the method in this application, this module has multiple functions such as data reception, parameter processing, range setting, and operating condition selection. It can efficiently receive and input design target operating parameters such as reactor rated thermal power, coolant inlet and outlet temperatures, and total mass flow rate. At the same time, it completes the precise setting of the bypass flow share analysis interval, the scientific selection of multiple operating points, and the flow distribution calculation based on the conservation of total flow rate. Ultimately, it provides unified, standardized, and accurate input conditions for subsequent core steady-state coupling calculations under different bypass flow share conditions, ensuring the rigor and operability of the entire sensitivity analysis process.

[0047] Step S3: Based on the physical-thermal coupling calculation model, apply the corresponding flow distribution boundary conditions to each bypass share value, and carry out the core steady-state physical-thermal coupling calculation until the power distribution, temperature field and flow distribution reach the convergence state, and obtain the thermal calculation data under each bypass share condition.

[0048] In this embodiment, before conducting steady-state coupled calculations, the precise application of boundary conditions must be completed. Specifically, the flow distribution boundary conditions determined in S2 for each bypass share value are completely and accurately imported into the physical-thermal-hydraulic coupled calculation model constructed in S1, ensuring that the boundary conditions are applied without omission or deviation. The application process of these boundary conditions strictly follows the basic physical laws of fluid flow and heat transfer, fully combining the flow area and flow resistance characteristics of the main core channel and various bypass channels, ensuring that the flow distribution state corresponding to each bypass share operating condition can realistically simulate the core flow field distribution and heat transfer characteristics under that bypass ratio in actual engineering, providing an inlet constraint that conforms to actual operating conditions for subsequent steady-state calculations, and ensuring the authenticity and effectiveness of the calculation results from the source.

[0049] After the boundary conditions are applied, in this embodiment of the application, a neutronics-thermal-hydraulic-fuel performance coupled calculation program, which has been verified through engineering practice and possesses high-precision calculation capabilities, is initiated to formally carry out the core steady-state physical-thermal coupling solution work. Throughout the entire calculation iteration process, the coupled calculation program synchronously iteratively solves multiple physics fields inside the core, specifically including the core power distribution, the flow distribution of coolant in the main channel and various bypass channels, and the temperature fields of core fuel elements, graphite reflector layers and other structural materials, as well as the coolant itself. The program fully considers the strong coupling relationship between neutronics, thermal-hydraulic, and fuel performance throughout the process, avoiding calculation deviations caused by solving a single physics field, and ensuring that the calculation results can comprehensively and accurately reflect the actual operating state of the core under the bypass share condition.

[0050] The steady-state energy conservation relationship of the reactor core is satisfied as follows:

[0051] in, For core thermal power, This is the coolant mass flow rate. The specific heat capacity at constant pressure of the coolant. This refers to the coolant outlet temperature. This refers to the coolant inlet temperature.

[0052] To ensure the stability and reliability of the calculation results, the embodiments of this application set up a strict convergence determination mechanism in the calculation process. This mechanism will monitor the dynamic changes of the core power distribution, temperature field and flow distribution in real time and continuously during the iteration process.

[0053] The convergence criterion adopts the maximum iterative deviation control of the temperature field, and the specific formula is as follows:

[0054] in, The core critical region temperature is calculated in the (k+1)th iteration. The core critical region temperature is calculated in the k-th iteration. This is the temperature convergence threshold. The value ranges from 1 to 10K, with 5K typically used in core fuel temperature calculations.

[0055] During the iteration process, the deviation between the current calculation result and the previous iteration result is compared in each iteration. The steady-state calculation under this condition is determined to have reached the convergence state only when the iteration deviation of the core power distribution is less than the preset convergence threshold, the iteration change of the temperature field in the key area of ​​the core meets the stability requirements, and the flow distribution of the main flow channel and the bypass flow channel always strictly follows the principle of total flow conservation and meets the preset convergence criteria. At this time, the iteration is terminated immediately to ensure the accuracy and effectiveness of the calculation results.

[0056] After the iteration terminates, this embodiment automatically outputs and stores the complete steady-state thermal calculation data corresponding to the bypass share condition. Following the same process, the steady-state coupling calculations for all bypass share conditions set in S2 are completed sequentially, ultimately forming a thermal calculation dataset covering all analysis conditions. This data comprehensively covers core thermal parameters such as power values ​​at key locations in the reactor core, temperature values ​​of fuel elements and structural materials, and coolant flow rates in each flow channel. The data is complete and reliable in accuracy, providing solid and comprehensive data support for the subsequent sensitivity analysis of target thermal parameters and determination of the upper limit of bypass share in S4. It is the core data source for the entire bypass sensitivity analysis process.

[0057] Furthermore, in this embodiment, a dedicated calculation execution module is provided to automate and standardize the steady-state coupling calculation under the aforementioned multi-sideflow share conditions. This module, as one of the core functional modules of the method, primarily drives the coupling calculation program. Following a preset calculation flow, it automatically reads each sideflow share condition and its corresponding flow allocation boundary conditions generated by the parameter setting module in S2, and sequentially initiates the steady-state simulation calculation for each condition. The entire process requires no manual intervention, effectively avoiding errors caused by manual operation. Simultaneously, it significantly improves the efficiency of multi-condition calculations and the consistency of calculation results, ensuring that the entire calculation process proceeds in a standardized, efficient, and orderly manner, providing a strong guarantee for the smooth progress of subsequent analysis work.

[0058] Step S4: Based on the thermal calculation data under each bypass share condition, analyze the sensitivity of the target thermal parameters to the bypass share, and determine the allowable upper limit of the bypass share under the premise of meeting the design safety limit and design performance target, so as to realize the determination of the bypass share limit of the pebble bed high temperature gas-cooled reactor.

[0059] In this embodiment, a standardized data analysis module is first used to deeply mine and precisely extract data from the complete multi-condition thermal calculation dataset output in stage S3, covering the entire analysis interval. Specifically, the extracted core indicators include the maximum fuel element temperature, which directly determines the reactor's safety baseline; the average fuel element temperature, reflecting the core's average thermal state; the maximum temperature of the graphite reflector layer, which is crucial for the long-term lifespan of structural materials; and the coolant outlet temperature, which is key to achieving high-temperature applications. It also includes key safety and performance thermal parameters such as the core power distribution, characterizing the overall power distribution of the core. The extraction process strictly adheres to data alignment and normalization principles to ensure direct comparability of thermal parameters of the same location and type under different operating conditions, laying an accurate and unified data foundation for subsequent pattern analysis.

[0060] After extracting and organizing the aforementioned key parameters, in this embodiment, the data analysis module uses the bypass fraction as the core independent variable and each extracted target thermal parameter as the dependent variable to construct and plot multi-dimensional parameter response curves. Through fitting and analyzing these curves, the system systematically and clearly understands the specific evolution trends, nonlinear fluctuation characteristics, and stable ranges of key indicators such as maximum fuel temperature, graphite temperature, and outlet temperature within different bypass fraction ranges, intuitively revealing the impact of bypass fraction changes on core thermal performance.

[0061] Based on this, the embodiments of this application further calculate and quantify the sensitivity of each target thermal parameter to changes in the bypass flow fraction, i.e., determine the sensitivity coefficient. The definition of the sensitivity coefficient can be flexibly selected according to the actual engineering analysis requirements, and its general mathematical expression is the ratio of the change in the target thermal parameter to the change in the bypass flow fraction, i.e.

[0062] Where S is the sensitivity coefficient of thermal parameters to the bypass flow ratio. The change in the target thermal parameters This represents the change in the sidestream share.

[0063] Taking temperature parameters as an example, the "temperature gradient with respect to bypass flow share" can be defined as a typical sensitivity coefficient. If the calculated temperature sensitivity coefficient for a certain operating condition is 3℃ / 1% bypass flow, it intuitively indicates that within this bypass flow share range, for every 1% increase in the bypass flow share, the corresponding key temperature indicators (such as the maximum temperature of the fuel element or the maximum temperature of the graphite reflector layer) will simultaneously increase by 3℃. By comparing the absolute values ​​of the sensitivity coefficients of different thermal parameters, the embodiments of this application can clearly and quantitatively identify the core control parameters that are most sensitive to changes in bypass flow share and respond most drastically, providing a clear focus for subsequent safety evaluation and design optimization.

[0064] After completing the sensitivity quantification analysis and clarifying the sensitivity of each parameter, in this embodiment, a rigorous multi-dimensional constraint verification and comprehensive evaluation process is executed through a specially designed safety evaluation module. This module rigorously compares the calculation results of all extracted target thermal parameters under each bypass share condition in S3 with the pre-set reactor design safety limits and allowable temperature limits for various in-core component materials, item by item and condition by condition. The safety constraints are satisfied as follows:

[0065] in, To calculate the highest temperature of the fuel element or graphite component, This refers to the allowable temperature limit for the corresponding material.

[0066] Ensure that every key parameter remains within safe limits under all analytical conditions, never crossing the safety red line. Simultaneously, accurately compare and verify the calculation results with the reactor's core design performance targets, such as achieving rated thermal power and the target outlet temperature of the primary coolant, to confirm that, under the premise of meeting safety constraints, the reactor's core performance indicators can basically meet or satisfy the design expectations.

[0067] After completing the comprehensive and rigorous constraint verification described above, this application embodiment, through trend analysis and multi-condition comprehensive verification, finally quantitatively determines the maximum allowable bypass flow fraction for the pebble bed high-temperature gas-cooled reactor core, i.e., the upper limit of the allowable bypass flow fraction. (Generally, the limit is no more than 15% in engineering practice). This upper limit is the core outcome of the entire bypass sensitivity analysis. It is not only a key control threshold to ensure the safe, stable, and design-targeted operation of the reactor, but also an important basis for guiding the optimization design of the core engineering. This determined upper limit of the bypass share can be directly fed back to key engineering aspects such as the refined structural design of in-core components, the precise control and optimization of core assembly gap dimensions, and the rational configuration of the primary circuit total flow, thereby achieving effective control of the bypass share. Through the method provided in the embodiments of this application, it can be ensured that the pebble bed high-temperature gas-cooled reactor, under stable operation at high power and high efficiency, not only strictly meets the core technical requirements of the high-temperature outlet of the primary circuit, but also comprehensively ensures the long-term, safe, and reliable operation of the reactor, ultimately achieving the accurate determination of the bypass share limit of the pebble bed high-temperature gas-cooled reactor, providing reliable and quantitative technical support for core optimization design and safe and efficient operation.

[0068] In the application of one embodiment of the present invention, the implementation process is as follows: This embodiment takes a pebble bed type high-temperature gas-cooled reactor design scheme A as the analysis object and conducts a sideflow share sensitivity analysis, such as... Figure 2 As shown, the specific steps are as follows: Step 1: Establish a refined physical-thermal coupling calculation model.

[0069] (1) Based on the design of the pebble bed type high temperature gas-cooled reactor core, a detailed geometric model is established, including the core pebble bed active area, side reflector layer, bottom reflector layer, graphite components and cold helium channels, control rod channels and other channels, to completely restore the overall structure and internal flow channel layout of the core. (2) In the model, the computational domain is meshed, and fuel cycle batches are set, such as... Figure 1 The image shows an example of computational mesh generation for a pebble bed type high-temperature reactor. Figure 3 It contains two parts: a.region number and b.batch number. Figure 3 (a) in the figure represents the distribution of region numbers in the computational region. Through a multi-region, multi-number grid, the radial and axial directions of the reactor core are finely discretized. Different numbered regions correspond to different functional regions such as the pebble bed active area, reflector layer, components and channels, providing a unified and accurate spatial computational basis for neutron physics calculations, burnup calculations and thermal coupling calculations. Figure 3 (b) in the figure represents the batch numbering arrangement of the fuel cycle, which is used to distinguish different stages of fuel loading, unloading and burning, so as to realize a refined simulation of the fuel cycle process; (3) Based on the core design parameters, set the detailed material layout for the core and surrounding areas, such as... Figure 4As shown in the figure, the entire structure of the reactor core, including the active zone, side reflector, bottom reflector, top graphite components, bottom support structure, control rod channels, cold helium rising channel, hot helium collection channel, and core shell, is fully displayed. Different regions are marked with different labels to distinguish material properties, and the spatial location and interface relationship of graphite reflector, fuel spherical bed, helium coolant, structural components, etc. are clearly defined, fully restoring the material distribution and thermal boundary conditions inside the reactor primary loop. (4) Establish a physics-thermal coupling calculation link. Neutron flux and power distributions are obtained through neutron physics calculations. This power distribution is then used as a heat source to perform solid heat conduction and fluid convection heat transfer calculations. The updated temperature field is fed back and the neutron cross-section parameters are corrected. Self-consistent convergence of the physical field and the thermal-hydraulic field is achieved through multiple iterative calculations. Specifically, the thermal calculations use two sets of meshes to handle solid heat conduction and fluid convection heat transfer respectively, such as... Figure 5 As shown, one set of meshes is for the solid structure and is used to solve the thermal conductivity and temperature field of solid regions such as fuel spheres, graphite reflective layers, and structural components; the other set of meshes is for the fluid region and is specifically used to solve the flow, distribution, convective heat transfer and pressure drop characteristics of helium in the flow channel. The two sets of meshes achieve temperature and heat flux density matching and transfer at the fluid-solid interface to ensure the accuracy and convergence of the coupled calculation. (5) In the established model, by adjusting the flow resistance coefficient or flow area of ​​the grid in the corresponding area such as graphite gaps and component gaps, the bypass flow capacity can be indirectly changed, thereby realizing the simulation of different bypass flow shares.

[0070] Step 2: Determine the boundary conditions and parameter range for bypass sensitivity analysis.

[0071] (1) Taking the high-temperature gas-cooled reactor design scheme A (Table 1) as an example, the target thermal power is 200MW, the primary loop helium outlet temperature is 750℃, the inlet temperature is 250℃, and the corresponding total mass flow rate is 77.0kg / ; Table 1 Example Design Scheme for Pellet Bed Type High-Temperature Gas-Cooled Reactor

[0072] (2) Based on the experience of similar high-temperature gas-cooled reactor projects and the requirements of conservative analysis, the side flow share analysis points are set at 10%, 20%, and 30%. The three analysis points basically cover the typical range from design expectation, moderate deviation to serious deviation, and can comprehensively reflect the influence law of side flow on core thermal safety. (3) For each bypass share condition, calculate the effective flow rate of the main channel. For example, when the total flow rate is 77.0 kg / s and the bypass share is 20%, the bypass flow rate is 15.4 kg / s and the effective flow rate of the main channel is 61.6 kg / s. This condition is achieved by adjusting the flow distribution of the corresponding area in the calculation.

[0073] Step 3: Execute steady-state thermal-hydraulic calculations under different bypass flow proportions.

[0074] Coupled calculations were performed for three operating conditions with bypass share of 10%, 20%, and 30%, respectively. Each condition started from the same initial state and was calculated until key parameters such as core power, temperature, and flow rate stabilized, reaching steady-state operating conditions. During the calculations, the reactor thermal power was kept constant at 200MW, coolant inlet temperature at 250℃, and total flow rate at 77.0kg / s; only the flow distribution ratio between the main stream and bypass stream was changed to ensure a strict basis for comparison between the various operating conditions.

[0075] Step 4: Extraction and analysis of key parameters for bypass sensitivity.

[0076] (1) Extract key thermal parameters such as the maximum temperature of fuel elements, the maximum temperature of graphite in the side reflector layer, and the helium outlet temperature from the calculation results of each operating condition to evaluate the core thermal safety level and operating performance. (2) Plot the relationship curves between key parameters and the sidestream share, such as Figure 6 As shown in the figure, with bypass flow ratio and coolant inlet temperature as independent variables and maximum fuel temperature as dependent variable, the figure clearly shows the variation of fuel temperature under different combinations of inlet temperatures (220℃, 230℃, 240℃, 250℃) and bypass flow ratios (10%, 20%, 30%). It can be intuitively identified that increasing bypass flow and increasing inlet temperature will significantly raise the fuel temperature, providing an intuitive basis for sensitivity analysis and safety evaluation. (3) Sensitivity analysis shows that when the inlet temperature is 250℃, the sideflow share increases from 10% to 30%, and the maximum fuel temperature increases from about 930℃ to about 1116℃. The change gradient is significant, which quantitatively reflects the important influence of the sideflow share on the core thermal state, cooling effect and fuel temperature level.

[0077] Step 5: Assess and determine the upper limit of the sidestream share.

[0078] (1) According to the design criteria of high temperature gas-cooled reactor, the maximum fuel temperature under normal operating conditions shall not exceed 1200℃ (taking into account the calculation uncertainty and operating margin), and the design target of 750℃ helium outlet temperature should be achieved as much as possible. (2) The calculation results show that when the bypass share is 30%, the maximum fuel temperature has reached 1116℃. If the calculation uncertainty and operation transient are considered, there is a risk of overheating, and the outlet temperature is difficult to maintain at 750℃. When the bypass share is 20%, the fuel temperature still has sufficient margin within the safety limit, and the outlet temperature is closer to the design target. (3) Considering the overall safety and performance indicators, it is recommended that the bypass flow share of the pebble bed type high temperature gas-cooled reactor be controlled below 20% and reduced as much as possible. This conclusion can provide a clear quantitative target for the design of the gap control of the reactor internal components and the design of the primary circuit system.

[0079] As can be seen from the above embodiments, this method can effectively quantify the impact of bypass flow on core thermal safety, identify potential design risks, and provide key inputs for design optimization. It is of great significance for ensuring the reliable design and efficient operation of pebble bed type high-temperature gas-cooled reactors.

[0080] Example 2 This invention provides a pebble bed type high-temperature gas-cooled reactor core bypass sensitivity analysis device. Figure 7 This is a schematic diagram of a pebble bed type high-temperature gas-cooled reactor core bypass sensitivity analysis device provided in an embodiment of the present invention. Figure 7 As shown, the device includes: The model building module 100 is used to establish a physical-thermal-engineering coupled calculation model that reflects the geometry and material arrangement of the core of the pebble bed type high-temperature gas-cooled reactor. The physical-thermal-engineering coupled calculation model is used to distinguish and characterize the flow area and flow resistance characteristics of the main channel and various bypass channels. The parameter setting module 200 is used to determine the design target parameters of the pebble bed high-temperature gas-cooled reactor, take the bypass flow share as the target analysis variable, set the analysis range of the bypass flow share and multiple bypass flow share values, and allocate the flow between the main flow channel and the bypass flow channel based on the total flow conservation. The coupling calculation module 300 is used to apply corresponding flow distribution boundary conditions to each bypass share value based on the physical-thermal coupling calculation model, carry out core steady-state physical-thermal coupling calculation, until the power distribution, temperature field and flow distribution reach the convergence state, and obtain thermal calculation data under each bypass share condition. The limit determination module 400 is used to analyze the sensitivity of the target thermal parameters to the bypass share based on the thermal calculation data under each bypass share condition, and determine the allowable upper limit of the bypass share under the premise of meeting the design safety limit and design performance target, so as to realize the determination of the bypass share limit of the pebble bed high temperature gas-cooled reactor.

[0081] Regarding the apparatus in the above embodiments, the specific manner in which each module performs its operation has been described in detail in the embodiments related to the method, and will not be elaborated upon here.

[0082] Example 3 To implement the methods of the above embodiments, the present invention also provides an electronic device, which includes a memory and a processor; wherein the processor reads executable program code stored in the memory to run a program corresponding to the executable program code, so as to implement the various steps of the methods described above.

[0083] Example 4 To implement the above embodiments, this application also proposes a non-transitory computer-readable storage medium storing a computer program thereon, which, when executed by a processor, implements the method described in the foregoing embodiments.

[0084] The above description is merely a preferred embodiment of the present invention and is not intended to limit the invention. Various modifications and variations can be made to the present invention by those skilled in the art. Any modifications, equivalent substitutions, improvements, etc., made within the spirit and principles of the present invention should be included within the scope of protection of the present invention.

[0085] In the description of this specification, the references to terms such as "one embodiment," "some embodiments," "example," "specific example," or "some examples," etc., indicate that a specific feature, structure, material, or characteristic described in connection with that embodiment or example is included in at least one embodiment or example of the present invention. In this specification, the illustrative expressions of the above terms do not necessarily refer to the same embodiment or example. Furthermore, the specific features, structures, materials, or characteristics described may be combined in any suitable manner in one or more embodiments or examples. Moreover, without contradiction, those skilled in the art can combine and integrate the different embodiments or examples described in this specification, as well as the features of different embodiments or examples.

[0086] Furthermore, the terms "first" and "second" are used for descriptive purposes only and should not be construed as indicating or implying relative importance or implicitly specifying the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include at least one of that feature. In the description of this invention, "a plurality of" means at least two, such as two, three, etc., unless otherwise explicitly specified.

Claims

1. A method for analyzing the bypass sensitivity of a pebble bed type high-temperature gas-cooled reactor core, characterized in that, include: A physical-thermal-engineering coupled calculation model is established to reflect the geometry and material arrangement of the core of a pebble bed type high-temperature gas-cooled reactor. The physical-thermal-engineering coupled calculation model is used to distinguish and characterize the flow area and flow resistance characteristics of the main flow channel and various bypass channels. The design target parameters of the pebble bed high-temperature gas-cooled reactor are determined, the bypass flow share is used as the target analysis variable, the analysis range of the bypass flow share and multiple bypass flow share values ​​are set, and the flow is allocated between the main flow channel and the bypass flow channel based on the total flow conservation. Based on the physical-thermal coupling calculation model, corresponding flow distribution boundary conditions are applied to each bypass share value, and core steady-state physical-thermal coupling calculations are carried out until the power distribution, temperature field and flow distribution reach a convergent state, and thermal calculation data under each bypass share condition are obtained. Based on the thermal calculation data under each bypass share condition, the sensitivity of the target thermal parameters to the bypass share is analyzed. Under the premise of meeting the design safety limit and design performance target, the allowable upper limit of the bypass share is determined, thus realizing the determination of the bypass share limit of the pebble bed high-temperature gas-cooled reactor.

2. The method according to claim 1, characterized in that, A physical-thermal-engineering coupling calculation model reflecting the core geometry and material arrangement of a pebble bed type high-temperature gas-cooled reactor is established, including: Collect and input the core geometry parameters, material arrangement parameters, fuel element characteristic parameters, and primary circuit system design parameters of the pebble bed type high temperature gas-cooled reactor; Select and employ validated nuclear reactor system analysis programs or combinations thereof to construct a refined computational model capable of simulating the multi-physics coupling behavior of neutronics, thermal-hydraulic, and fuel performance within the reactor core.

3. The method according to claim 2, characterized in that, The design target parameters of the pebble bed high-temperature gas-cooled reactor are determined, with the bypass flow fraction as the target analysis variable. The analysis range of the bypass flow fraction and multiple bypass flow fraction values ​​are set, and the flow rate is allocated between the main flow channel and the bypass flow channel based on the total flow rate conservation, including: Determine and input the design target parameters for the reactor rated thermal power, primary coolant inlet temperature, target coolant outlet temperature, and primary total mass flow rate; The sidestream share is defined as the target analysis variable, and the sidestream share is defined as the ratio of sidestream flow to total flow. Based on engineering experience, reference data of similar reactor types, and conservative analysis principles, the sideflow share analysis range covering the design expected value to the maximum possible deviation value is determined and set, and a preset discrete sideflow share value is selected as the analysis condition. Based on the total flow conservation relationship, the main flow and the bypass flow are calculated and allocated for each discrete bypass share operating condition, forming the flow allocation boundary conditions for the corresponding operating condition.

4. The method according to claim 3, characterized in that, Based on the aforementioned physical-thermal coupling calculation model, corresponding flow distribution boundary conditions are applied to each bypass share value, and steady-state physical-thermal coupling calculations of the reactor core are performed until the power distribution, temperature field, and flow distribution reach a convergent state. Thermal calculation data for each bypass share condition are then obtained, including: Apply the flow distribution boundary conditions corresponding to each bypass share operating condition to the established physical-thermal-hydraulic coupling calculation model; The neutronics-thermal-hydraulic-fuel performance coupled calculation program was launched to simultaneously iteratively solve the core power distribution, coolant flow distribution, and temperature field of core and structural materials. The calculation is continuously iterated until the core power distribution, temperature field and flow distribution all meet the preset convergence criteria, and the steady-state thermal calculation data corresponding to each bypass flow share condition are output and stored.

5. The method according to claim 4, characterized in that, Based on the thermal calculation data under various bypass flow share conditions, the sensitivity of the target thermal parameters to the bypass flow share is analyzed, including: Extract the target safety and performance parameters of fuel element maximum temperature, fuel element average temperature, graphite reflector maximum temperature, coolant outlet temperature, and core power distribution from the calculation results of each operating condition; Using the bypass flow share as the independent variable and each target thermal parameter as the dependent variable, the variation law of the target parameters with the bypass flow share is fitted and analyzed. Calculate and determine the sensitivity coefficient of the target parameter to the bypass share. The sensitivity coefficient is expressed as the ratio of the change in the target parameter to the change in the bypass share. Identify and determine the target control parameter that is most significantly affected by the bypass.

6. The method according to claim 5, characterized in that, And, provided that the design safety limits and design performance objectives are met, determine the permissible upper limit for the bypass flow share, including: The calculation results of the target parameters under each bypass share operating condition are compared and constrained with the reactor design safety limits, material allowable temperature limits and design performance targets item by item. Under the constraint that all target parameters meet the design safety limits and basically achieve the design performance targets, the maximum allowable bypass flow share for this reactor type is determined through trend analysis and operating condition verification. The determined maximum bypass share is used as the upper limit and control target of the bypass share in the core design stage, and is used to provide feedback guidance for the design of in-core components, control of gap size, and optimization of primary loop total flow design.

7. A pebble bed type high-temperature gas-cooled reactor core bypass sensitivity analysis device, characterized in that, include: The model building module is used to establish a physical-thermal-engineering coupled calculation model that reflects the geometry and material arrangement of the core of the pebble bed type high-temperature gas-cooled reactor. The physical-thermal-engineering coupled calculation model is used to distinguish and characterize the flow area and flow resistance characteristics of the main flow channel and various bypass channels. The parameter setting module is used to determine the design target parameters of the pebble bed high-temperature gas-cooled reactor, with the bypass flow share as the target analysis variable, setting the analysis range of the bypass flow share and multiple bypass flow share values, and distributing the flow between the main flow channel and the bypass flow channel based on the total flow conservation. The coupling calculation module is used to apply corresponding flow distribution boundary conditions to each bypass share value based on the physical-thermal coupling calculation model, carry out core steady-state physical-thermal coupling calculation, until the power distribution, temperature field and flow distribution reach the convergence state, and obtain thermal calculation data under each bypass share condition. The limit determination module is used to analyze the sensitivity of the target thermal parameters to the bypass share based on the thermal calculation data under each bypass share condition, and determine the allowable upper limit of the bypass share under the premise of meeting the design safety limit and design performance target, so as to realize the determination of the bypass share limit of the pebble bed high temperature gas-cooled reactor.

8. The apparatus according to claim 7, characterized in that, The parameter setting module is also used for: Determine and input the design target parameters for the reactor rated thermal power, primary coolant inlet temperature, target coolant outlet temperature, and primary total mass flow rate; The sidestream share is defined as the target analysis variable, and the sidestream share is defined as the ratio of sidestream flow to total flow. Based on engineering experience, reference data of similar reactor types, and conservative analysis principles, the sideflow share analysis range covering the design expected value to the maximum possible deviation value is determined and set, and several discrete sideflow share values ​​are selected as analysis conditions. Based on the total flow conservation relationship, the main flow and the bypass flow are calculated and allocated for each discrete bypass share operating condition, forming the flow allocation boundary conditions for the corresponding operating condition.

9. An electronic device, characterized in that, Including processor and memory; The processor reads executable program code stored in the memory to run a program corresponding to the executable program code, so as to implement the method as described in any one of claims 1-6.

10. A non-transitory computer-readable storage medium having a computer program stored thereon, characterized in that, When the program is executed by the processor, it implements the method as described in any one of claims 1-6.

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