Method for determining departure from nucleate boiling ratio design limit of mixed core

Abstract

The present application provides a method for determining a departure from nucleate boiling ratio design limit of a mixed core, and a product. The determination method comprises: acquiring a first departure from nucleate boiling ratio design limit of a full core of a mixed core; determining a target fuel assembly among at least two types of fuel assemblies of the mixed core, a departure from nucleate boiling ratio of the target fuel assembly representing a minimum departure from nucleate boiling ratio of the mixed core; and determining a departure from nucleate boiling ratio design limit of the mixed core on the basis of the relationship between the departure from nucleate boiling ratio of the target fuel assembly and the first departure from nucleate boiling ratio design limit. In the present application, by determining the target fuel assembly, the departure from nucleate boiling ratio of which represents the minimum departure from nucleate boiling ratio of the mixed core, and determining the departure from nucleate boiling ratio design limit of the mixed core on the basis of the relationship between the departure from nucleate boiling ratio of the target fuel assembly and the first departure from nucleate boiling ratio design limit, the efficiency and accuracy of determining the departure from nucleate boiling ratio design limit of the mixed core can be improved.

Description

A method for determining the deviation of hybrid reactor core from the design limit of nucleation-boiling ratio Technical Field

[0001] This application relates to the field of nuclear reactor technology, specifically to a method and product for determining the deviation of a hybrid reactor core from the design limit of the boiling-bubbling ratio. Background Technology

[0002] The Departure from Nucleate Boiling Ratio (DNBR) design limit is fundamental to nuclear reactor safety assessment. During reactor operation, the minimum DNBR value of the reactor core needs to be monitored in real time to determine whether it exceeds the DNBR design limit, in order to prevent the core from deviating from nucleate boiling (DNB) under accident conditions.

[0003] Current methods for determining DNBR design limits mainly focus on determining the DNBR design limits for a full-core reactor consisting of the same fuel assembly. For hybrid cores consisting of different fuel assemblies, there is currently no efficient method for determining DNBR design limits.

[0004] Improving the efficiency and accuracy of determining the deviation of the hybrid reactor core from the design limit of the nucleation-boiling ratio has become an urgent problem to be solved. Summary of the Invention

[0005] The main objective of this application is to provide a method and product for determining the deviation of a hybrid reactor core from the design limit of the nucleation-boiling ratio, aiming to improve the efficiency and accuracy of determining the deviation of a hybrid reactor core from the design limit of the nucleation-boiling ratio.

[0006] This application provides a method for determining the deviation from the design limit of the nucleus-boiling ratio in a hybrid reactor core. The hybrid reactor core includes at least two fuel assemblies, and the entire core of the hybrid reactor core is composed of a first fuel assembly among the at least two fuel assemblies. The determination method includes: obtaining a first deviation from the design limit of the nucleus-boiling ratio of the entire core; determining a target fuel assembly among the at least two fuel assemblies, wherein the deviation from the nucleus-boiling ratio of the target fuel assembly characterizes the minimum deviation from the nucleus-boiling ratio of the hybrid reactor core; and determining the deviation from the design limit of the nucleus-boiling ratio of the hybrid reactor core based on the relationship between the deviation from the nucleus-boiling ratio of the target fuel assembly and the first deviation from the design limit of the nucleus-boiling ratio.

[0007] In one embodiment, the deviation nucleus boiling ratio of the target fuel assembly includes the deviation nucleus boiling ratios corresponding to multiple first critical heat flux density test points of the target fuel assembly; the step of determining the design limit of the deviation nucleus boiling ratio of the hybrid reactor core based on the relationship between the deviation nucleus boiling ratio of the target fuel assembly and the design limit of the first deviation nucleus boiling ratio includes: determining the proportion of a second critical heat flux density test point based on the relationship between the deviation nucleus boiling ratios corresponding to the multiple first critical heat flux density test points and the design limit of the first deviation nucleus boiling ratio; the second critical heat flux density test point is the test point among the multiple first critical heat flux density test points whose deviation nucleus boiling ratio is greater than the design limit of the first deviation nucleus boiling ratio; comparing the proportion of the second critical heat flux density test point with a preset proportion; if the proportion of the second critical heat flux density test point is higher than or equal to the preset proportion, then the design limit of the first deviation nucleus boiling ratio is determined as the design limit of the deviation nucleus boiling ratio of the hybrid reactor core.

[0008] In one embodiment, after comparing the proportion of the second critical heat flux density test point with a preset proportion, the determination method further includes: if the proportion of the second critical heat flux density test point is lower than the preset proportion, then the first deviation nucleus boiling ratio design limit is updated to the second deviation nucleus boiling ratio design limit, and the step of determining the proportion of the second critical heat flux density test point based on the relationship between the deviation nucleus boiling ratios corresponding to the plurality of first critical heat flux density test points and the first deviation nucleus boiling ratio design limit is returned to be executed until the proportion of the second critical heat flux density test point is higher than or equal to the preset proportion, and the first deviation nucleus boiling ratio design limit at this time is determined as the deviation nucleus boiling ratio design limit of the hybrid reactor core; wherein, the second deviation nucleus boiling ratio design limit is lower than the first deviation nucleus boiling ratio design limit.

[0009] In one embodiment, before determining the proportion of the second critical heat flux density test point based on the relationship between the deviation nucleus boiling ratio corresponding to the plurality of first critical heat flux density test points and the design limit of the first deviation nucleus boiling ratio, the determination method further includes: obtaining the critical heat flux density test values ​​corresponding to the plurality of first critical heat flux density test points; determining the predicted critical heat flux density values ​​corresponding to the plurality of third critical heat flux density test points based on the thermal parameters of the target fuel assembly and the thermal diffusivity of the target fuel assembly, combined with the critical heat flux density relationship of the first fuel assembly; for each first critical heat flux density test point, determining the deviation nucleus boiling ratio corresponding to the first critical heat flux density test point as the ratio of the critical heat flux density test value corresponding to the first critical heat flux density test point to the predicted critical heat flux density value corresponding to the fourth critical heat flux density test point; wherein, the fourth critical heat flux density test point is the test point among the plurality of third critical heat flux density test points that corresponds to the first critical heat flux density test point; the thermal parameters of the plurality of third critical heat flux density test points are calculated based on the sub-channel thermal safety analysis model of the hybrid reactor core.

[0010] In one embodiment, before determining the ratio of the critical heat flux density test value corresponding to the first critical heat flux density test point to the critical heat flux density prediction value corresponding to the fourth critical heat flux density test point as the deviation from the nucleation-boiling ratio corresponding to the first critical heat flux density test point, the determination method further includes: for each first critical heat flux density test point, determining the deviation between the first critical heat flux density test point and the plurality of third critical heat flux density test points; and determining the third critical heat flux density test point corresponding to the deviation within a preset range as the fourth critical heat flux density test point.

[0011] In one embodiment, determining the target fuel assembly among the at least two fuel assemblies includes: identifying the fuel assembly with the largest thermal diffusivity among the at least two fuel assemblies as the target fuel assembly.

[0012] This application also provides a system for determining the deviation from the design limit of the nucleus-boiling ratio in a hybrid reactor core. The hybrid reactor core includes at least two types of fuel assemblies, and the entire core of the hybrid reactor core is composed of a first fuel assembly among the at least two fuel assemblies. The determination system includes an acquisition module, a fuel assembly determination module, and a design limit determination module. The acquisition module is used to acquire the first deviation from the design limit of the nucleus-boiling ratio of the entire core. The fuel assembly determination module is used to determine a target fuel assembly among the at least two fuel assemblies, and the deviation from the nucleus-boiling ratio of the target fuel assembly characterizes the minimum deviation from the nucleus-boiling ratio of the hybrid reactor core. The design limit determination module is used to determine the deviation from the design limit of the nucleus-boiling ratio of the hybrid reactor core based on the relationship between the deviation from the nucleus-boiling ratio of the target fuel assembly and the first deviation from the design limit of the nucleus-boiling ratio.

[0013] This application also provides an electronic device, which includes a memory and a processor. The memory stores a computer program, and the processor executes the computer program to implement the above-mentioned method for determining the deviation of the hybrid reactor core from the design limit of the core boiling ratio.

[0014] This application also provides a computer-readable storage medium storing a computer program that, when executed by a processor, implements the above-described method for determining the deviation of the hybrid reactor core from the design limit of the nucleus boiling ratio.

[0015] This application also provides a computer program product, which is stored in a storage medium, and when executed by at least one processor, implements the above-described method for determining the deviation of the hybrid core from the design limit of the core boiling ratio.

[0016] This application provides a method and product for determining the design limit of the deviation nucleus boiling ratio of a hybrid reactor core. By determining the target fuel assembly whose deviation nucleus boiling ratio characterizes the minimum deviation nucleus boiling ratio of the hybrid reactor core, and based on the relationship between the deviation nucleus boiling ratio of the target fuel assembly and the first design limit of the deviation nucleus boiling ratio, the design limit of the deviation nucleus boiling ratio of the hybrid reactor core is determined, which can improve the efficiency and accuracy of determining the design limit of the deviation nucleus boiling ratio of the hybrid reactor core. Attached Figure Description

[0017] Figure 1 is a flowchart illustrating an embodiment of the method for determining the deviation of the hybrid core from the design limit of the nucleation-boiling ratio provided in this application;

[0018] Figure 2 is a schematic flowchart of an embodiment of the method for determining the deviation of the hybrid core from the design limit of the nucleation-boiling ratio provided in this application;

[0019] Figure 3 is a schematic diagram of the system for determining the deviation of the hybrid core from the design limit of the nucleation-boiling ratio provided in this application;

[0020] Figure 4 is a schematic diagram of the structure of an embodiment of the electronic device provided in this application;

[0021] Figure 5 is a schematic diagram of another embodiment of the electronic device provided in this application. Detailed Implementation

[0022] The technical solutions of the embodiments of this application will be clearly described below with reference to the accompanying drawings. Obviously, the described embodiments are only some, not all, of the embodiments of this application. All other embodiments obtained by those skilled in the art based on the embodiments of this application are within the scope of protection of this application.

[0023] The terms "first," "second," etc., used in the specification and claims of this application are used to distinguish similar objects and not to describe a specific order or sequence. It should be understood that such use of data can be interchanged where appropriate so that embodiments of this application can be implemented in orders other than those illustrated or described herein, and the objects distinguished by "first," "second," etc., are generally of the same class and the number of objects is not limited; for example, a first object can be one or more. Furthermore, in the specification and claims, "and / or" indicates at least one of the connected objects, and the character " / " generally indicates that the preceding and following objects are in an "or" relationship.

[0024] The method for determining the deviation of the hybrid reactor core from the design limit of the nucleus-boiling ratio provided in this application embodiment can be applied to a terminal, a server, or software running on either a terminal or a server. In some embodiments, the terminal can be a smartphone, tablet, laptop, desktop computer, etc.; the server can be configured as an independent physical server, a server cluster or distributed system composed of multiple physical servers, or a cloud server providing basic cloud computing services such as cloud services, cloud databases, cloud computing, cloud functions, cloud storage, network services, cloud communication, middleware services, domain name services, security services, CDN, and big data and artificial intelligence platforms; the software can be an application that implements the method for determining the deviation of the hybrid reactor core from the design limit of the nucleus-boiling ratio, etc., but is not limited to the above forms.

[0025] The method for determining the deviation of the design limit of the nucleation-boiling ratio of the hybrid reactor core provided in this application will be described in detail below with reference to the accompanying drawings and specific embodiments.

[0026] Please refer to Figure 1. This application provides a method for determining the deviation of a hybrid reactor core from the design limit of the core-boiling ratio. The hybrid reactor core includes at least two types of fuel assemblies, and the entire hybrid reactor core is composed of the first fuel assembly of at least two types of fuel assemblies. The determination method includes:

[0027] Step S101: Obtain the first deviation from the design limit of the nucleus boiling ratio for the entire reactor core;

[0028] Step S102: Determine the target fuel assembly from at least two fuel assemblies, wherein the deviation nucleus boiling ratio of the target fuel assembly characterizes the minimum deviation nucleus boiling ratio of the mixed core;

[0029] Step S103: Determine the design limit of the deviation nucleus boiling ratio of the mixed core based on the relationship between the deviation nucleus boiling ratio of the target fuel assembly and the first deviation nucleus boiling ratio design limit.

[0030] This application provides a method and product for determining the design limit of the deviation nucleus boiling ratio of a hybrid reactor core. By determining the target fuel assembly whose deviation nucleus boiling ratio characterizes the minimum deviation nucleus boiling ratio of the hybrid reactor core, and based on the relationship between the deviation nucleus boiling ratio of the target fuel assembly and the first design limit of the deviation nucleus boiling ratio, the design limit of the deviation nucleus boiling ratio of the hybrid reactor core is determined, which can improve the efficiency and accuracy of determining the design limit of the deviation nucleus boiling ratio of the hybrid reactor core.

[0031] Optionally, the first deviation nucleus boiling ratio design limit in step S101 above is determined based on a deterministic method or a statistical method. The deterministic method uses the maximum value among the deviation nucleus boiling ratios corresponding to all critical heat flux density test points in the entire reactor core as the design limit for the entire reactor core's deviation nucleus boiling ratio. The statistical method determines the deviation nucleus boiling ratio under different power, flow, and other parameters through sampling under normal operating conditions and accident conditions of the entire reactor core, and uses the maximum value among the determined deviation nucleus boiling ratios as the design limit for the entire reactor core's deviation nucleus boiling ratio.

[0032] In one embodiment, determining the target fuel assembly among at least two types of fuel assemblies in step S102 includes:

[0033] The fuel assembly with the largest thermal diffusivity among at least two fuel assemblies is identified as the target fuel assembly.

[0034] Optionally, if the deviation between the critical heat flux density test points of the at least two fuel assemblies is within the target range, the fuel assembly with the largest thermal diffusivity among the at least two fuel assemblies is selected as the target fuel assembly. The deviation between the critical heat flux density test points of the at least two fuel assemblies being within the target range indicates that the critical heat flux density test values ​​of the at least two fuel assemblies are close. Since the predicted critical heat flux density is proportional to the thermal diffusivity, the deviation from nucleus boiling ratio of the target fuel assembly, calculated using its critical heat flux density test value and predicted critical heat flux density, can be used to characterize the minimum deviation from nucleus boiling ratio of the mixed reactor core.

[0035] Alternatively, the deviation from the nucleation boiling ratio is determined by the following formula: DNBR = CHF 试验值 / CHF 预测值 ;

[0036] Wherein, DNBR is the deviation from the nucleation boiling ratio, CHF 试验值 The critical heat flux density (CHF) is the experimental value. 预测值 This is the predicted value of the critical heat flux density.

[0037] This application embodiment compares the thermal diffusivity of at least two fuel assemblies and identifies the fuel assembly with the largest thermal diffusivity among the at least two fuel assemblies as the target fuel assembly. This improves the efficiency and accuracy of identifying the target fuel assembly, and consequently improves the efficiency and accuracy of determining the deviation from the design limit of the nucleus boiling ratio of the hybrid reactor core.

[0038] In another embodiment, determining the target fuel assembly among at least two types of fuel assemblies in step S102 above includes:

[0039] The deviation ratio from nucleation boiling for at least two fuel assemblies was determined through experiments;

[0040] The fuel assembly with the smallest deviation from the nucleation-boiling ratio among at least two fuel assemblies is identified as the target fuel assembly.

[0041] The embodiments of this application determine the deviation nucleus boiling ratio of at least two fuel assemblies through experiments, and identify the fuel assembly with the smallest deviation nucleus boiling ratio among the at least two fuel assemblies as the target fuel assembly. This can improve the efficiency and accuracy of determining the target fuel assembly, and thus improve the efficiency and accuracy of determining the design limit of the deviation nucleus boiling ratio of the hybrid reactor core.

[0042] Optionally, the deviation nucleus boiling ratio of the target fuel assembly in step S103 above includes the deviation nucleus boiling ratio corresponding to multiple first critical heat flux density test points of the target fuel assembly.

[0043] Each first critical heat flux density test point corresponds to a critical heat flux density test condition for the target fuel assembly, under which the target fuel assembly will exhibit critical heat flux density phenomena. The critical heat flux density test conditions include thermal parameters such as the pressure, temperature, flow rate, and gas content of the coolant fluid in the mixed reactor core.

[0044] As shown in Figure 2, step S103 above, which determines the design limit of the deviation nucleus boiling ratio of the mixed reactor core based on the relationship between the deviation nucleus boiling ratio of the target fuel assembly and the first deviation nucleus boiling ratio design limit, may include:

[0045] Step S201: Based on the relationship between the deviation nucleus boiling ratio and the design limit of the first deviation nucleus boiling ratio corresponding to multiple first critical heat flux density test points, determine the proportion of the second critical heat flux density test points; wherein, the second critical heat flux density test points are the test points among multiple first critical heat flux density test points whose deviation nucleus boiling ratio is greater than the design limit of the first deviation nucleus boiling ratio;

[0046] The proportion of the second critical heat flux density test point is compared with the preset proportion. Step S202: Determine whether the proportion of the second critical heat flux density test point is lower than the preset proportion.

[0047] If the proportion of the second critical heat flux density test point is higher than or equal to the preset proportion, then step S203 is executed: the first deviation nucleus boiling ratio design limit is determined as the deviation nucleus boiling ratio design limit of the hybrid core;

[0048] If the proportion of the second critical heat flux density test point is lower than the preset proportion, then step S204 is executed: the first deviation nucleus boiling ratio design limit is updated to the second deviation nucleus boiling ratio design limit, and the execution of step S201 is returned until the proportion of the second critical heat flux density test point is higher than or equal to the preset proportion, and the first deviation nucleus boiling ratio design limit at this time is determined as the deviation nucleus boiling ratio design limit of the hybrid core.

[0049] The second deviation from the design limit for the nucleus boiling ratio is lower than the first deviation from the design limit for the nucleus boiling ratio.

[0050] In step S201 above, the proportion of the second critical heat flux density test points is the ratio of the number of second critical heat flux density test points to the number of first critical heat flux density test points. Optionally, the preset proportion is 95%.

[0051] This application embodiment uses the comparison results of the proportion of the second critical heat flux density test point among multiple first critical heat flux density test points with a preset proportion to determine the first deviation nucleus boiling ratio design limit as the deviation nucleus boiling ratio design limit for the hybrid reactor core, or reduces the first deviation nucleus boiling ratio design limit, and finally determines a first deviation nucleus boiling ratio design limit that is smaller than the deviation nucleus boiling ratio of 95% of the second critical heat flux density test points, and uses this first deviation nucleus boiling ratio design limit as the deviation nucleus boiling ratio design limit for the hybrid reactor core, which can improve the efficiency and accuracy of determining the deviation nucleus boiling ratio design limit for the hybrid reactor core.

[0052] In step S204 above, updating the first deviation from the design limit for the nucleation-boiling ratio to the second deviation from the design limit for the nucleation-boiling ratio may include:

[0053] The first deviation from the design limit of the nucleus-boiling ratio is reduced by a preset amount to obtain the second deviation from the design limit of the nucleus-boiling ratio.

[0054] The preset amplitude can be set to a value between 0.01 and 0.02. If the proportion of the second critical heat flux density test point is lower than the preset proportion, the first deviation from the design limit of the nucleation-boiling ratio can be reduced by 0.01 to 0.02 to obtain the second deviation from the design limit of the nucleation-boiling ratio.

[0055] In this embodiment of the application, when the proportion of the second critical heat flux density test point among multiple first critical heat flux density test points is less than a preset proportion, the first deviation nucleus boiling ratio design limit is reduced by a preset magnitude. Finally, a first deviation nucleus boiling ratio design limit smaller than the deviation nucleus boiling ratio of 95% of the second critical heat flux density test points is determined, and this first deviation nucleus boiling ratio design limit is used as the deviation nucleus boiling ratio design limit for the hybrid reactor core. This not only improves the efficiency and accuracy of determining the deviation nucleus boiling ratio design limit for the hybrid reactor core, but also ensures the practicality of the determined deviation nucleus boiling ratio design limit for the hybrid reactor core.

[0056] In one embodiment, before determining the proportion of the second critical heat flux density test point based on the relationship between the deviation nucleus boiling ratio corresponding to multiple first critical heat flux density test points and the first deviation nucleus boiling ratio design limit, the method for determining the deviation nucleus boiling ratio design limit of the hybrid reactor core provided in this application embodiment further includes:

[0057] Obtain the critical heat flux density test values ​​corresponding to multiple first critical heat flux density test points;

[0058] Based on the thermal parameters of multiple third critical heat flux density test points of the target fuel assembly and the thermal diffusivity of the target fuel assembly, combined with the critical heat flux density relationship of the first fuel assembly, the predicted critical heat flux density values ​​corresponding to multiple third critical heat flux density test points are determined.

[0059] For each first critical heat flux density test point, the ratio of the critical heat flux density test value corresponding to the first critical heat flux density test point to the critical heat flux density prediction value corresponding to the fourth critical heat flux density test point is determined as the deviation from nucleation boiling ratio corresponding to the first critical heat flux density test point.

[0060] Among them, the fourth critical heat flux density test point is the test point corresponding to the first critical heat flux density test point among multiple third critical heat flux density test points; the thermal parameters of multiple third critical heat flux density test points are calculated based on the sub-channel thermal safety analysis model of the hybrid core.

[0061] This application embodiment obtains the critical heat flux density test value corresponding to each first critical heat flux density test point of the target fuel assembly, and determines the critical heat flux density prediction value corresponding to each third critical heat flux density test point based on the thermal parameters of each third critical heat flux density test point and the thermal diffusivity of the target fuel assembly, combined with the critical heat flux density relationship of the first fuel assembly. Furthermore, based on the determination of the third critical heat flux density test point corresponding to the first critical heat flux density test point, the deviation nucleus boiling ratio corresponding to each first critical heat flux density test point of the target fuel assembly can be quickly and accurately determined. This improves the efficiency and accuracy of determining the deviation nucleus boiling ratio design limit of the hybrid reactor core based on the relationship between the deviation nucleus boiling ratio of the target fuel assembly and the first deviation nucleus boiling ratio design limit.

[0062] Optionally, obtaining the critical heat flux density test values ​​corresponding to multiple first critical heat flux density test points includes: obtaining the thermal parameter range of the hybrid reactor core; within the thermal parameter range, fixing the first thermal parameters of the coolant fluid in the hybrid reactor core, and adjusting other thermal parameters of the coolant fluid by gradually increasing the heating power of the test device in a stepwise manner; when the heating element of the target fuel assembly test section experiences a rapid rise in wall temperature and becomes difficult to stabilize under a certain set of thermal parameters, it is determined that the target fuel assembly has experienced a critical heat flux density phenomenon, and the test conditions composed of this set of thermal parameters are determined as a first critical heat flux density test point of the target fuel assembly, and the heat flux density at this time is determined as the critical heat flux density test value corresponding to the first critical heat flux density test point. The thermal parameter range of the hybrid reactor core can be determined based on the in-core characteristics of the hybrid reactor core under normal operating conditions and accident conditions.

[0063] The embodiments of this application can accurately determine the critical heat flux density test values ​​corresponding to multiple first critical heat flux density test points through critical heat flux density tests, thereby improving the efficiency and accuracy of determining the deviation of the core boiling ratio from the design limit of the hybrid reactor core.

[0064] Optionally, the sub-channel thermal safety analysis model of the hybrid reactor core is obtained by dividing the hybrid reactor core into multiple small and interconnected channels, through which mass, momentum and energy are exchanged.

[0065] In one embodiment, the above-mentioned determination of the predicted critical heat flux density values ​​corresponding to the multiple third critical heat flux density test points based on the thermal parameters of the target fuel assembly at multiple third critical heat flux density test points and the thermal diffusivity of the target fuel assembly, combined with the critical heat flux density relationship of the first fuel assembly, includes:

[0066] For each third critical heat flux density test point, the thermal parameters of the third critical heat flux density test point and the thermal diffusivity of the target fuel assembly are substituted into the critical heat flux density relationship of the first fuel assembly to obtain the predicted critical heat flux density value corresponding to the third critical heat flux density test point.

[0067] Optionally, the critical heat flux density relationship for the first fuel assembly is CHF. 预测值 = f(P,G,X,TDC,dg), where CHF 预测值 denoted as the predicted critical heat flux density corresponding to the third critical heat flux density test point, and P, G, and X are the thermal parameters of the third critical heat flux density test point calculated by the sub-channel thermal safety analysis model based on the hybrid core, where P is the pressure of the coolant fluid, G is the flow rate of the coolant fluid, X is the gas content of the coolant fluid, TDC is the thermal diffusivity of the target fuel assembly, and dg is the grid height of the hybrid core.

[0068] This application embodiment, by substituting the thermal parameters of the third critical heat flux density test point and the thermal diffusivity of the target fuel assembly into the critical heat flux density relationship of the first fuel assembly, can accurately determine the predicted critical heat flux density value corresponding to the third critical heat flux density test point, thereby improving the efficiency and accuracy of determining the deviation of the core boiling ratio design limit of the hybrid reactor core.

[0069] In one embodiment, before determining the ratio of the critical heat flux density test value corresponding to the first critical heat flux density test point to the critical heat flux density prediction value corresponding to the fourth critical heat flux density test point as the deviation nucleus boiling ratio corresponding to the first critical heat flux density test point, the method for determining the design limit value of the deviation nucleus boiling ratio of the hybrid reactor core provided in this application embodiment further includes:

[0070] For each first critical heat flux density test point, determine the deviation between the first critical heat flux density test point and multiple third critical heat flux density test points;

[0071] The third critical heat flux density test point corresponding to the deviation within the preset range is determined as the fourth critical heat flux density test point.

[0072] In this application embodiment, for each first critical heat flux density test point, based on the deviation between the first critical heat flux density test point and multiple third critical heat flux density test points, the fourth critical heat flux density test point corresponding to the first critical heat flux density test point among the multiple third critical heat flux density test points can be accurately determined. This improves the accuracy of determining the deviation nucleus boiling ratio corresponding to the first critical heat flux density test point based on the critical heat flux density test value corresponding to the first critical heat flux density test point and the critical heat flux density prediction value corresponding to the fourth critical heat flux density test point. Consequently, it improves the efficiency and accuracy of determining the deviation nucleus boiling ratio design limit of the hybrid reactor core.

[0073] Optionally, the deviation between the first critical heat flux density test point and multiple third critical heat flux density test points includes at least one of the following:

[0074] Positional deviation between the first position and each second position on the target fuel assembly;

[0075] The deviation of the same thermal parameter between the first critical heat flux density test point and each third critical heat flux density test point;

[0076] The first position is the location on the target fuel assembly where the critical heat flux density phenomenon occurs, corresponding to the first critical heat flux density test point, and the second position is the location on the target fuel assembly where the critical heat flux density phenomenon occurs, corresponding to the third critical heat flux density test point.

[0077] Optionally, the target range and the preset range can be the same range or different ranges.

[0078] Optionally, the preset range includes at least one of the following: -10 cm ≤ positional deviation ≤ 10 cm; -10% ≤ deviation of the same thermal parameter ≤ 10%.

[0079] Optionally, when the thermal parameters include temperature, pressure, flow rate, and gas content, the following conditions must be met simultaneously to determine that -10% ≤ deviation of the same thermal parameter ≤ 10%: -10% ≤ temperature deviation ≤ 10%; -10% ≤ pressure deviation ≤ 10%; -10% ≤ flow rate deviation ≤ 10%; -10% ≤ gas content deviation ≤ 10%.

[0080] Based on the positional deviation between the first position and each second position on the target fuel assembly, and / or the deviation of the same thermal parameter between the first critical heat flux density test point and each third critical heat flux density test point, the embodiments of this application can accurately determine the fourth critical heat flux density test point corresponding to the first critical heat flux density test point among multiple third critical heat flux density test points. This can improve the accuracy of determining the deviation nucleus boiling ratio corresponding to the first critical heat flux density test point based on the critical heat flux density test value corresponding to the first critical heat flux density test point and the critical heat flux density prediction value corresponding to the fourth critical heat flux density test point. As a result, it can improve the efficiency and accuracy of determining the deviation nucleus boiling ratio design limit of the hybrid reactor core.

[0081] Please refer to Figure 3. This application embodiment also provides a system for determining the deviation of the hybrid reactor core from the design limit of the nucleus-boiling ratio (DNBR determination system) 300, which can realize the above-mentioned method for determining the deviation of the hybrid reactor core from the design limit of the nucleus-boiling ratio. The hybrid reactor core includes at least two fuel assemblies, and the entire core of the hybrid reactor core is composed of the first fuel assembly of at least two fuel assemblies. The system includes an acquisition module 301, a fuel assembly determination module 302, and a design limit determination module 303.

[0082] The acquisition module 301 is used to acquire the first deviation from the design limit of the core boiling ratio for the entire reactor core;

[0083] The fuel assembly determination module 302 is used to determine a target fuel assembly among at least two fuel assemblies, and the deviation nucleus boiling ratio of the target fuel assembly characterizes the minimum deviation nucleus boiling ratio of the mixed reactor core.

[0084] The design limit determination module 303 is used to determine the design limit of the deviated nucleus boiling ratio of the mixed reactor core based on the relationship between the deviated nucleus boiling ratio of the target fuel assembly and the first deviated nucleus boiling ratio design limit.

[0085] The system for determining the deviation of the hybrid reactor core from the design limit of the nucleus-boiling ratio provided in this application embodiment can realize all the steps of the above-described method embodiment for determining the deviation of the hybrid reactor core from the design limit of the nucleus-boiling ratio, and can achieve the same technical effect. To avoid repetition, it will not be described again here.

[0086] Optionally, as shown in FIG4, this application embodiment also provides an electronic device 400, including a processor 401 and a memory 402. The memory 402 stores a program or instructions that can run on the processor 401. When the program or instructions are executed by the processor 401, they implement the various steps of the above-described method embodiment for determining the deviation of the hybrid reactor core from the design limit of the nucleus boiling ratio, and can achieve the same technical effect. To avoid repetition, they will not be described again here. It should be noted that the electronic device in this application embodiment includes the above-described mobile electronic device and non-mobile electronic device.

[0087] Figure 5 is a schematic diagram of the hardware structure of an electronic device implementing an embodiment of this application. The electronic device includes:

[0088] The processor 501 can be implemented using a general-purpose CPU (Central Processing Unit), microprocessor, application-specific integrated circuit (ASIC), or one or more integrated circuits, and is used to execute relevant programs to implement the technical solutions provided in the embodiments of this application.

[0089] The memory 502 can be implemented in the form of read-only memory (ROM), static storage device, dynamic storage device, or random access memory (RAM). The memory 502 can store the operating system and other application programs. When the technical solutions provided in the embodiments of this specification are implemented through software or firmware, the relevant program code is stored in the memory 502 and is called by the processor 501 to execute the method for determining the deviation of the hybrid reactor core from the design limit of the nucleus boiling ratio in the embodiments of this application.

[0090] The input / output interface 503 is used to implement information input and output;

[0091] The communication interface 504 is used to enable communication and interaction between this device and other devices. Communication can be achieved through wired means (such as USB, network cable, etc.) or wireless means (such as mobile network, WIFI, Bluetooth, etc.).

[0092] Bus 505 transmits information between various components of the device (e.g., processor 501, memory 502, input / output interface 503, and communication interface 504);

[0093] The processor 501, memory 502, input / output interface 503, and communication interface 504 are connected to each other within the device via bus 505.

[0094] The electronic device provided in this application embodiment can implement each step of the above-described method embodiment for determining the deviation of the core boiling ratio from the design limit of the hybrid reactor core, and can achieve the same technical effect. To avoid repetition, it will not be described again here.

[0095] This application also provides a computer-readable storage medium storing a program or instructions. When the program or instructions are executed by a processor, they implement the various steps of the above-described method embodiment for determining the deviation of the hybrid core from the design limit of the nucleus boiling ratio, and achieve the same technical effect. To avoid repetition, they will not be described again here.

[0096] The processor is the processor in the electronic device described in the above embodiments. The computer-readable storage medium includes computer-readable storage media such as computer read-only memory (ROM), random access memory (RAM), magnetic disk, or optical disk.

[0097] This application also provides a chip, which includes a processor and a communication interface. The communication interface and the processor are coupled. The processor is used to run programs or instructions to implement the various steps of the above-described method embodiment for determining the deviation of the hybrid core from the design limit of the boiling ratio, and can achieve the same technical effect. To avoid repetition, it will not be described again here.

[0098] It should be understood that the chip mentioned in the embodiments of this application may also be referred to as a system-on-a-chip, system chip, chip system, or system-on-a-chip, etc.

[0099] This application provides a computer program product stored in a storage medium. The program product is executed by at least one processor to implement the various steps of the above-described method embodiment for determining the deviation of the core boiling ratio from the design limit of the hybrid reactor core, and can achieve the same technical effect. To avoid repetition, it will not be described again here.

[0100] It should be noted that, in this document, the terms "comprising," "including," or any other variations thereof are intended to cover non-exclusive inclusion, such that a process, method, article, or apparatus that comprises a list of elements includes not only those elements but also other elements not expressly listed, or elements inherent to such a process, method, article, or apparatus. Without further limitations, an element defined by the phrase "comprising one..." does not exclude the presence of other identical elements in the process, method, article, or apparatus that includes that element. Furthermore, it should be noted that the scope of the methods and apparatuses in the embodiments of this application is not limited to performing functions in the order shown or discussed, but may also include performing functions substantially simultaneously or in the reverse order, depending on the functions involved. For example, the described methods may be performed in a different order than described, and various steps may be added, omitted, or combined. Additionally, features described with reference to certain examples may be combined in other examples.

[0101] Through the above description of the embodiments, those skilled in the art can clearly understand that the methods of the above embodiments can be implemented by means of software plus necessary general-purpose hardware platforms. Of course, they can also be implemented by hardware, but in many cases the former is a better implementation method. Based on this understanding, the technical solution of this application, in essence, or the part that contributes to the prior art, can be embodied in the form of a computer software product. This computer software product is stored in a storage medium (such as ROM / RAM, magnetic disk, optical disk) and includes several instructions to cause a terminal (which may be a mobile phone, computer, server, or network device, etc.) to execute the methods described in the various embodiments of this application.

[0102] The embodiments of this application have been described above with reference to the accompanying drawings. However, this application is not limited to the specific embodiments described above. The specific embodiments described above are merely illustrative and not restrictive. Those skilled in the art can make many other forms under the guidance of this application without departing from the spirit and scope of the claims, and all of these forms are within the protection scope of this application.

Claims

1. A method for determining the deviation of a hybrid reactor core from the design limit of the nucleation-boiling ratio, characterized in that, The hybrid reactor core includes at least two fuel assemblies, and the entire core of the hybrid reactor core is composed of a first fuel assembly of the at least two fuel assemblies. The method for determining this composition includes: Obtain the first deviation from the design limit of the nucleus boiling ratio for the entire reactor core; A target fuel assembly is determined among the at least two fuel assemblies, and the deviation from nucleus boiling ratio of the target fuel assembly characterizes the minimum deviation from nucleus boiling ratio of the hybrid reactor core; The design limit for the deviation nucleus boiling ratio of the hybrid reactor core is determined based on the relationship between the deviation nucleus boiling ratio of the target fuel assembly and the first deviation nucleus boiling ratio design limit.

2. The determination method as described in claim 1, characterized in that, The deviation nucleus boiling ratio of the target fuel assembly includes the deviation nucleus boiling ratio corresponding to multiple first critical heat flux density test points of the target fuel assembly; The step of determining the design limit of the deviation nucleus boiling ratio of the hybrid reactor core based on the relationship between the deviation nucleus boiling ratio of the target fuel assembly and the first deviation nucleus boiling ratio design limit includes: Based on the relationship between the deviation from the nucleus boiling ratio and the design limit of the first deviation from the nucleus boiling ratio corresponding to the plurality of first critical heat flux density test points, the proportion of the second critical heat flux density test points is determined; the second critical heat flux density test points are the test points among the plurality of first critical heat flux density test points whose deviation from the nucleus boiling ratio is greater than the design limit of the first deviation from the nucleus boiling ratio. The proportion of the second critical heat flux density test point is compared with the preset proportion; If the proportion of the second critical heat flux density test point is higher than or equal to the preset proportion, then the first deviation from the design limit of the nucleus boiling ratio is determined as the deviation from the design limit of the nucleus boiling ratio of the hybrid core.

3. The determination method as described in claim 2, characterized in that, After the step of comparing the proportion of the second critical heat flux density test point with the preset proportion, the determination method further includes: If the proportion of the second critical heat flux density test point is lower than the preset proportion, then the first deviation nucleus boiling ratio design limit is updated to the second deviation nucleus boiling ratio design limit, and the process returns to the step of determining the proportion of the second critical heat flux density test point based on the relationship between the deviation nucleus boiling ratio corresponding to the plurality of first critical heat flux density test points and the first deviation nucleus boiling ratio design limit, until the proportion of the second critical heat flux density test point is higher than or equal to the preset proportion, and the first deviation nucleus boiling ratio design limit at this time is determined as the deviation nucleus boiling ratio design limit of the hybrid reactor core; Wherein, the second deviation from the design limit of the nucleus boiling ratio is lower than the first deviation from the design limit of the nucleus boiling ratio.

4. The determination method as described in claim 2, characterized in that, Before determining the proportion of the second critical heat flux density test point based on the relationship between the deviation nucleus boiling ratio corresponding to the plurality of first critical heat flux density test points and the design limit of the first deviation nucleus boiling ratio, the determination method further includes: Obtain the critical heat flux density test values ​​corresponding to the plurality of first critical heat flux density test points; Based on the thermal parameters of multiple third critical heat flux density test points of the target fuel assembly and the thermal diffusivity of the target fuel assembly, combined with the critical heat flux density relationship of the first fuel assembly, the predicted critical heat flux density values ​​corresponding to the multiple third critical heat flux density test points are determined. For each first critical heat flux density test point, the ratio of the critical heat flux density test value corresponding to the first critical heat flux density test point to the critical heat flux density prediction value corresponding to the fourth critical heat flux density test point is determined as the deviation nucleation boiling ratio corresponding to the first critical heat flux density test point. The fourth critical heat flux density test point is the test point among the plurality of third critical heat flux density test points that corresponds to the first critical heat flux density test point; the thermal parameters of the plurality of third critical heat flux density test points are calculated based on the sub-channel thermal safety analysis model of the hybrid core.

5. The determination method as described in claim 4, characterized in that, Before determining the ratio of the experimental critical heat flux density value corresponding to the first critical heat flux density test point to the predicted critical heat flux density value corresponding to the fourth critical heat flux density test point as the deviation from the nucleus boiling ratio corresponding to the first critical heat flux density test point, the determination method further includes: For each of the first critical heat flux density test points, the deviation between the first critical heat flux density test point and the plurality of third critical heat flux density test points is determined; The third critical heat flux density test point corresponding to the deviation within the preset range is determined as the fourth critical heat flux density test point.

6. The determination method as described in claim 1, characterized in that, Determining the target fuel assembly among the at least two fuel assemblies includes: The fuel assembly with the largest thermal diffusivity among the at least two fuel assemblies is identified as the target fuel assembly.

7. A system for determining deviations from the design limit of the nucleus boiling ratio in a hybrid reactor core, characterized in that, The hybrid reactor core includes at least two fuel assemblies, and the entire core of the hybrid reactor core is composed of a first fuel assembly of the at least two fuel assemblies. The determining system includes an acquisition module, a fuel assembly determining module, and a design limit determining module. The acquisition module is used to acquire the first deviation from the design limit of the nucleation-boiling ratio of the entire core. The fuel assembly determination module is used to determine a target fuel assembly among the at least two fuel assemblies, and the deviation nucleus boiling ratio of the target fuel assembly characterizes the minimum deviation nucleus boiling ratio of the hybrid reactor core. The design limit determination module is used to determine the design limit of the deviated nucleus boiling ratio of the hybrid reactor core based on the relationship between the deviated nucleus boiling ratio of the target fuel assembly and the first design limit of the deviated nucleus boiling ratio.

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