Method and product for determining a mixed core excursion from nucleate boiling to design limit

Abstract

The application provides a method and product for determining a mixed core deviation from nucleate boiling ratio design limit value, and the method comprises the following steps: obtaining a first deviation from nucleate boiling ratio design limit value of a full core of a mixed core; determining a target fuel assembly in at least two fuel assemblies of the mixed core, and the deviation from nucleate boiling ratio of the target fuel assembly represents the minimum deviation from nucleate boiling ratio of the mixed core; and determining the deviation from nucleate boiling ratio design limit value of the mixed core according to the relationship between the deviation from nucleate boiling ratio of the target fuel assembly and the first deviation from nucleate boiling ratio design limit value. The application determines the target fuel assembly whose deviation from nucleate boiling ratio represents the minimum deviation from nucleate boiling ratio of the mixed core, and determines the deviation from nucleate boiling ratio design limit value of the mixed core based on the relationship between the deviation from nucleate boiling ratio of the target fuel assembly and the first deviation from nucleate boiling ratio design limit value, so that the efficiency and accuracy of determining the deviation from nucleate boiling ratio design limit value of the mixed core can be improved.

Description

TECHNICAL FIELD

[0001] The present application relates to the technical field of nuclear reactors, in particular to a method for determining a departure from nucleate boiling ratio design limit of a mixed core and a product. BACKGROUND

[0002] The departure from nucleate boiling ratio (DNBR) design limit is the basis for safety evaluation of a nuclear reactor. During the operation of the nuclear reactor, the minimum DNBR value of the core needs to be monitored in real time, and it is determined whether the minimum DNBR value is greater than the DNBR design limit, so as to prevent the occurrence of departure from nucleate boiling (DNB) in the core under accident conditions.

[0003] The current method for determining the DNBR design limit mainly focuses on determining the DNBR design limit of the full core composed of the same fuel assembly. There is currently no efficient method for determining the DNBR design limit of a mixed core composed of different fuel assemblies.

[0004] How to improve the efficiency and accuracy of determining the departure from nucleate boiling ratio design limit of a mixed core has become a problem to be solved. SUMMARY

[0005] The main purpose of the embodiments of the present application is to provide a method for determining the departure from nucleate boiling ratio design limit of a mixed core and a product, which aims to improve the efficiency and accuracy of determining the departure from nucleate boiling ratio design limit of a mixed core.

[0006] The present application provides a method for determining the departure from nucleate boiling ratio design limit of a mixed core, the mixed core comprising at least two fuel assemblies, a full core of the mixed core being composed of a first fuel assembly among the at least two fuel assemblies, the method comprising: obtaining a first departure from nucleate boiling ratio design limit of the full core; determining a target fuel assembly among the at least two fuel assemblies, 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 according to a relationship between the departure from nucleate boiling ratio of the target fuel assembly and the first departure from nucleate boiling ratio design limit.

[0007] In an embodiment, the deviation nucleate boiling ratios of the target fuel assembly include deviation nucleate boiling ratios corresponding to a plurality of first critical heat flux test points of the target fuel assembly; the step of determining the deviation nucleate boiling ratio design limit of the mixed core according to the relationship between the deviation nucleate boiling ratio of the target fuel assembly and the first deviation nucleate boiling ratio design limit includes: determining a proportion of second critical heat flux test points according to the relationship between the deviation nucleate boiling ratios corresponding to the plurality of first critical heat flux test points and the first deviation nucleate boiling ratio design limit; the second critical heat flux test points are test points of the plurality of first critical heat flux test points whose deviation nucleate boiling ratios are greater than the first deviation nucleate boiling ratio design limit; comparing the proportion of the second critical heat flux test points with a preset proportion; if the proportion of the second critical heat flux test points is higher than or equal to the preset proportion, the first deviation nucleate boiling ratio design limit is determined as the deviation nucleate boiling ratio design limit of the mixed core.

[0008] In an embodiment, after the step of comparing the proportion of the second critical heat flux test points with a preset proportion, the determination method further includes: if the proportion of the second critical heat flux test points is lower than the preset proportion, updating the first deviation nucleate boiling ratio design limit to a second deviation nucleate boiling ratio design limit, and returning to perform the step of determining the proportion of second critical heat flux test points according to the relationship between the deviation nucleate boiling ratios corresponding to the plurality of first critical heat flux test points and the first deviation nucleate boiling ratio design limit until the proportion of the second critical heat flux test points is higher than or equal to the preset proportion, and determining the first deviation nucleate boiling ratio design limit at this time as the deviation nucleate boiling ratio design limit of the mixed core; wherein the second deviation nucleate boiling ratio design limit is lower than the first deviation nucleate boiling ratio design limit.

[0009] In an embodiment, before the determining the proportion of the second critical heat flux test point according to the relationship between the deviation nucleate boiling ratios corresponding to the plurality of first critical heat flux test points and the first deviation nucleate boiling ratio design limit, the determining method further comprises: obtaining the critical heat flux test value corresponding to each of the plurality of first critical heat flux test points; determining the critical heat flux prediction value corresponding to each of the plurality of third critical heat flux test points of the target fuel assembly, according to the thermal parameters of the plurality of third critical heat flux test points of the target fuel assembly and the thermal diffusivity of the target fuel assembly, and combining the critical heat flux relationship of the first fuel assembly; for each first critical heat flux test point, determining the ratio of the critical heat flux test value corresponding to the first critical heat flux test point to the critical heat flux prediction value corresponding to the fourth critical heat flux test point as the deviation nucleate boiling ratio corresponding to the first critical heat flux test point; wherein the fourth critical heat flux test point is the test point corresponding to the first critical heat flux test point in the plurality of third critical heat flux test points; the thermal parameters of the plurality of third critical heat flux test points are calculated based on the sub-channel thermal safety analysis model of the mixed core.

[0010] In an embodiment, before the determining the ratio of the critical heat flux test value corresponding to the first critical heat flux test point to the critical heat flux prediction value corresponding to the fourth critical heat flux test point as the deviation nucleate boiling ratio corresponding to the first critical heat flux test point, the determining method further comprises: for each of the first critical heat flux test points, determining the deviation of the first critical heat flux test point from the plurality of third critical heat flux test points; determining the third critical heat flux test point corresponding to the deviation within the preset range as the fourth critical heat flux test point.

[0011] In an embodiment, the determining the target fuel assembly from the at least two fuel assemblies comprises: determining the fuel assembly with the largest thermal diffusivity from the at least two fuel assemblies as the target fuel assembly.

[0012] The application further provides a system for determining a mixed core departure from nucleate boiling ratio design limit value, the mixed core comprising at least two fuel assemblies, a full core of the mixed core consisting of first fuel assemblies in the at least two fuel assemblies, the system comprising an acquisition module, a fuel assembly determination module and a design limit value determination module; the acquisition module is configured to acquire a first departure from nucleate boiling ratio design limit value of the full core; the fuel assembly determination module is configured to determine a target fuel assembly in the at least two fuel assemblies, a departure from nucleate boiling ratio of the target fuel assembly representing a minimum departure from nucleate boiling ratio of the mixed core; and the design limit value determination module is configured to determine the departure from nucleate boiling ratio design limit value of the mixed core according to a relationship between the departure from nucleate boiling ratio of the target fuel assembly and the first departure from nucleate boiling ratio design limit value.

[0013] The application further provides an electronic device, comprising a memory and a processor, the memory storing a computer program, and the processor implementing the above-mentioned method for determining a mixed core departure from nucleate boiling ratio design limit value when executing the computer program.

[0014] The application further provides a computer readable storage medium storing a computer program, and the computer program implementing the above-mentioned method for determining a mixed core departure from nucleate boiling ratio design limit value when executed by a processor.

[0015] The application further provides a computer program product stored in a storage medium, and the computer program product implementing the above-mentioned method for determining a mixed core departure from nucleate boiling ratio design limit value when executed by at least one processor.

[0016] The application provides a method and product for determining a mixed core departure from nucleate boiling ratio design limit value, which can improve the efficiency and accuracy of determining the mixed core departure from nucleate boiling ratio design limit value by determining a target fuel assembly whose departure from nucleate boiling ratio represents a minimum departure from nucleate boiling ratio of the mixed core, and determining the mixed core departure from nucleate boiling ratio design limit value based on a relationship between the departure from nucleate boiling ratio of the target fuel assembly and a first departure from nucleate boiling ratio design limit value. BRIEF DESCRIPTION OF DRAWINGS

[0017] Figure 1 FIG. 1 is a flowchart of an embodiment of the method for determining a mixed core departure from nucleate boiling ratio design limit value provided by the application;

[0018] Figure 2 FIG. 2 is a specific flowchart of an embodiment of the method for determining a mixed core departure from nucleate boiling ratio design limit value provided by the application;

[0019] Figure 3is a structural schematic diagram of a system for determining a mixed core deviation from the design limit of nucleate boiling provided in the present application;

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

[0021] Figure 5 is a structural schematic diagram of another embodiment of an electronic device provided in the present application. DETAILED DESCRIPTION

[0022] The technical solutions in the embodiments of the present application will be clearly described below with reference to the drawings in the embodiments of the present application. Obviously, the described embodiments are only some of the embodiments of the present application, but not all of them. Based on the embodiments in the present application, all other embodiments obtained by a person of ordinary skill in the art belong to the scope of protection of the present application.

[0023] The terms "first", "second", and the like in the specification and claims of the present application are used to distinguish similar objects, and are not used to describe a specific order or sequence. It should be understood that the data used in this way can be interchanged under appropriate circumstances, so that the embodiments of the present application can be implemented in an order other than those illustrated or described herein, and the objects distinguished by "first", "second", etc. are usually a category and do not limit the number of objects, for example, the first object can be one or more. In addition, "and / or" in the specification and claims means at least one of the connected objects, and the character " / " generally represents an "or" relationship between the front and rear associated objects.

[0024] The mixed core deviation from the design limit of nucleate boiling determination method provided in the embodiments of the present application can be applied to a terminal, can also be applied to a server side, and can also be software running in a terminal or a server side. In some embodiments, the terminal can be a smart phone, a tablet computer, a notebook computer, a desktop computer, etc.; the server side can be configured as a separate physical server, can also be configured as a server cluster or a distributed system formed by multiple physical servers, can also be configured as a cloud server providing cloud services, cloud databases, cloud computing, cloud functions, cloud storage, network services, cloud communication, middleware services, domain name services, security services, CDNs, and basic cloud computing services such as big data and artificial intelligence platforms; and the software can be an application that implements the mixed core deviation from the design limit of nucleate boiling determination method, etc., but is not limited to the above forms.

[0025] The mixed core deviation from the design limit of nucleate boiling determination method provided in the embodiments of the present application will be described in detail below with reference to the drawings and specific embodiments.

[0026] Please refer to Figure 1The embodiment of the present application provides a method for determining a deviation nucleate boiling ratio design limit value of a mixed core, the mixed core comprising at least two fuel assemblies, and the whole core of the mixed core being composed of first fuel assemblies in the at least two fuel assemblies, and the method comprising the following steps:

[0027] Step S101: obtaining a first deviation nucleate boiling ratio design limit value of the whole core;

[0028] Step S102: determining a target fuel assembly in the at least two fuel assemblies, and the deviation nucleate boiling ratio of the target fuel assembly representing a minimum deviation nucleate boiling ratio of the mixed core;

[0029] Step S103: determining the deviation nucleate boiling ratio design limit value of the mixed core according to a relationship between the deviation nucleate boiling ratio of the target fuel assembly and the first deviation nucleate boiling ratio design limit value.

[0030] The method and product for determining the deviation nucleate boiling ratio design limit value of the mixed core provided by the embodiment of the present application can improve the efficiency and accuracy of determining the deviation nucleate boiling ratio design limit value of the mixed core by determining the target fuel assembly whose deviation nucleate boiling ratio represents the minimum deviation nucleate boiling ratio of the mixed core, and determining the deviation nucleate boiling ratio design limit value of the mixed core based on the relationship between the deviation nucleate boiling ratio of the target fuel assembly and the first deviation nucleate boiling ratio design limit value.

[0031] Optionally, the first deviation nucleate boiling ratio design limit value in the step S101 is determined based on a determinism method or a statistical method. The determinism method is to take the maximum value in the deviation nucleate boiling ratios corresponding to all critical heat flux density test points in the whole core as the deviation nucleate boiling ratio design limit value of the whole core; and the statistical method is to determine the deviation nucleate boiling ratios under different power and flow parameters by sampling under normal operation conditions and accident conditions of the whole core, and take the maximum value in the determined deviation nucleate boiling ratios as the deviation nucleate boiling ratio design limit value of the whole core.

[0032] In an embodiment, the step S102 of determining the target fuel assembly in the at least two fuel assemblies comprises the following steps:

[0033] The fuel assembly with the maximum thermal diffusion coefficient in the at least two fuel assemblies is determined as the target fuel assembly.

[0034] Optionally, in the case that the deviation between the critical heat flux 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 test points of the at least two fuel assemblies within the target range indicates that the critical heat flux test values of the at least two fuel assemblies are close, and since the critical heat flux prediction value is proportional to the thermal diffusivity, the departure from nucleate boiling ratio of the target fuel assembly calculated by the critical heat flux test value of the target fuel assembly and the critical heat flux prediction value thereof can be used to represent the minimum departure from nucleate boiling ratio of the mixed core.

[0035] Optionally, the departure from nucleate boiling ratio is determined by the following formula:

[0036] DNBR = CHF 试验值 / CHF 预测值

[0037] wherein DNBR is the departure from nucleate boiling ratio, CHF 试验值 is the critical heat flux test value, and CHF 预测值 is the critical heat flux prediction value.

[0038] The embodiments of the present application can improve the efficiency and accuracy of determining the target fuel assembly by comparing the thermal diffusivities of the at least two fuel assemblies and determining the target fuel assembly as the fuel assembly with the largest thermal diffusivity among the at least two fuel assemblies, and further improve the efficiency and accuracy of determining the departure from nucleate boiling ratio design limit value of the mixed core.

[0039] In another embodiment, the step S102 of determining the target fuel assembly among the at least two fuel assemblies includes:

[0040] determining the departure from nucleate boiling ratio of the at least two fuel assemblies by experiment;

[0041] determining the target fuel assembly as the fuel assembly with the smallest departure from nucleate boiling ratio among the at least two fuel assemblies.

[0042] The embodiments of the present application can improve the efficiency and accuracy of determining the target fuel assembly by determining the departure from nucleate boiling ratio of the at least two fuel assemblies by experiment and determining the target fuel assembly as the fuel assembly with the smallest departure from nucleate boiling ratio among the at least two fuel assemblies, and further improve the efficiency and accuracy of determining the departure from nucleate boiling ratio design limit value of the mixed core.

[0043] Optionally, the departure from nucleate boiling ratio of the target fuel assembly in the step S103 includes a plurality of first critical heat flux test point corresponding departure from nucleate boiling ratios of the target fuel assembly.

[0044] Each first critical heat flux test point corresponds to a critical heat flux test condition of the target fuel assembly, and the target fuel assembly will have a critical heat flux phenomenon under the test condition. The critical heat flux test condition includes thermal parameters such as the pressure, temperature, flow rate, and gas content of the coolant fluid in the mixed core.

[0045] As shown in FIG. 1, the step S103 of determining the departure from nucleate boiling ratio design limit of the mixed core according to the relationship between the departure from nucleate boiling ratio of the target fuel assembly and the first departure from nucleate boiling ratio design limit can include: Figure 2

[0046] Step S201: determining the proportion of the second critical heat flux test point according to the relationship between the departure from nucleate boiling ratio corresponding to the plurality of first critical heat flux test points and the first departure from nucleate boiling ratio design limit; wherein the second critical heat flux test point is a test point in the plurality of first critical heat flux test points whose departure from nucleate boiling ratio is greater than the first departure from nucleate boiling ratio design limit;

[0047] Step S202: determining whether the proportion of the second critical heat flux test point is lower than the preset proportion by comparing the proportion of the second critical heat flux test point with the preset proportion;

[0048] If the proportion of the second critical heat flux test point is higher than or equal to the preset proportion, step S203 is performed to determine the first departure from nucleate boiling ratio design limit as the departure from nucleate boiling ratio design limit of the mixed core;

[0049] If the proportion of the second critical heat flux test point is lower than the preset proportion, step S204 is performed to update the first departure from nucleate boiling ratio design limit to the second departure from nucleate boiling ratio design limit, and return to step S201 until the proportion of the second critical heat flux test point is higher than or equal to the preset proportion, and determine the first departure from nucleate boiling ratio design limit at this time as the departure from nucleate boiling ratio design limit of the mixed core;

[0050] The second departure from nucleate boiling ratio design limit is lower than the first departure from nucleate boiling ratio design limit.

[0051] The proportion of the second critical heat flux test point in step S201 is the ratio of the number of the second critical heat flux test points to the number of the first critical heat flux test points. Optionally, the preset proportion is 95%.

[0052] ​The embodiment of the present application determines the first departure from nucleate boiling ratio design limit value as the departure from nucleate boiling ratio design limit value of the mixed reactor core, or reduces the first departure from nucleate boiling ratio design limit value, finally determines the first departure from nucleate boiling ratio design limit value which is smaller than the departure from nucleate boiling ratio of 95% of the second critical heat flux test points, and takes the first departure from nucleate boiling ratio design limit value as the departure from nucleate boiling ratio design limit value of the mixed reactor core, which can improve the efficiency and accuracy of determining the departure from nucleate boiling ratio design limit value of the mixed reactor core.

[0053] The step S204 of updating the first departure from nucleate boiling ratio design limit value to the second departure from nucleate boiling ratio design limit value can include:

[0054] The first departure from nucleate boiling ratio design limit value is reduced by the preset amplitude to obtain the second departure from nucleate boiling ratio design limit value;

[0055] The preset amplitude can be 0.01-0.02. In the case that the proportion of the second critical heat flux test point is lower than the preset proportion, the first departure from nucleate boiling ratio design limit value can be reduced by 0.01-0.02 to obtain the second departure from nucleate boiling ratio design limit value.

[0056] In the case that the proportion of the second critical heat flux test point in the plurality of first critical heat flux test points is less than the preset proportion, the embodiment of the present application reduces the first departure from nucleate boiling ratio design limit value by the preset amplitude, finally determines the first departure from nucleate boiling ratio design limit value which is smaller than the departure from nucleate boiling ratio of 95% of the second critical heat flux test points, and takes the first departure from nucleate boiling ratio design limit value as the departure from nucleate boiling ratio design limit value of the mixed reactor core, which not only can improve the efficiency and accuracy of determining the departure from nucleate boiling ratio design limit value of the mixed reactor core, but also can ensure the practicability of the determined departure from nucleate boiling ratio design limit value of the mixed reactor core.

[0057] In an embodiment, before determining the proportion of the second critical heat flux test point according to the relationship between the departure from nucleate boiling ratio corresponding to the plurality of first critical heat flux test points and the first departure from nucleate boiling ratio design limit value, the method for determining the departure from nucleate boiling ratio design limit value of the mixed reactor core provided by the embodiment of the present application further includes:

[0058] Obtaining critical heat flux test values corresponding to the plurality of first critical heat flux test points;

[0059] According to the thermal parameters of the plurality of third critical heat flux density test points of the target fuel assembly and the thermal diffusivity of the target fuel assembly, and in combination with the critical heat flux density relationship of the first fuel assembly, critical heat flux density prediction values corresponding to the plurality of third critical heat flux density test points are determined;

[0060] For each first critical heat flux density test point, a ratio of a critical heat flux density test value corresponding to the first critical heat flux density test point to a critical heat flux density prediction value corresponding to the fourth critical heat flux density test point is determined as a departure from nucleate boiling ratio corresponding to the first critical heat flux density test point;

[0061] The fourth critical heat flux density test point is a test point corresponding to the first critical heat flux density test point in the plurality of third critical heat flux density test points, and the thermal parameters of the plurality of third critical heat flux density test points are calculated based on a sub-channel thermal safety analysis model of the mixed core.

[0062] The embodiments of the present application can quickly and accurately determine the departure from nucleate boiling ratio corresponding to each first critical heat flux density test point of the target fuel assembly by obtaining the critical heat flux density test value corresponding to each first critical heat flux density test point of the target fuel assembly, and determining 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, in combination with the critical heat flux density relationship of the first fuel assembly, and further based on the third critical heat flux density test point corresponding to the first critical heat flux density test point, thereby improving the efficiency and accuracy of determining the departure from nucleate boiling ratio design limit of the mixed core based on the relationship between the departure from nucleate boiling ratio of the target fuel assembly and the first departure from nucleate boiling ratio design limit.

[0063] Optionally, the above-mentioned obtaining of the critical heat flux density test values corresponding to the plurality of first critical heat flux density test points comprises: obtaining a thermal parameter range of the mixed core; in the thermal parameter range, fixing a first thermal parameter of the coolant fluid of the mixed core, and adjusting other thermal parameters of the coolant fluid by gradually increasing the heating power of the test device in a step-by-step manner, when the heating element of the target fuel assembly test section appears a wall temperature runaway and is difficult to stabilize under a certain set of thermal parameters, it is determined that the target fuel assembly has a critical heat flux density phenomenon, and the test condition composed of the set of thermal parameters is determined as a first critical heat flux density test point of the target fuel assembly, and the heat flux 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 mixed core can be determined according to the in-core characteristics of the mixed core under normal operating conditions and accident conditions.

[0064] The embodiment of the application can accurately determine the critical heat flux density test values corresponding to the plurality of first critical heat flux density test points through the critical heat flux density test, thereby improving the efficiency and accuracy of determining the departure from nucleate boiling ratio design limit of the mixed core.

[0065] Optionally, the sub-channel thermal safety analysis model of the mixed core is obtained by dividing the mixed core into a plurality of small and interconnected channels, and there is exchange of mass, momentum and energy between the channels.

[0066] In an embodiment, the critical heat flux density predicted values corresponding to the plurality of third critical heat flux density test points are determined according to the thermal parameters of the plurality of third critical heat flux density test points of the target fuel assembly and the thermal diffusivity of the target fuel assembly, in combination with the critical heat flux density relationship of the first fuel assembly, and the method comprises the following steps:

[0067] 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 critical heat flux density predicted value corresponding to the third critical heat flux density test point.

[0068] Optionally, the critical heat flux density relationship of the first fuel assembly is CHF 预测值 =f(P,G,X,TDC,dg), wherein CHF 预测值 is the critical heat flux density predicted value corresponding to the third critical heat flux density test point, P, G and X are the thermal parameters of the third critical heat flux density test point calculated based on the sub-channel thermal safety analysis model of the mixed core, wherein P is the pressure of the coolant fluid, G is the flow rate of the coolant fluid, and X is the air content of the coolant fluid, TDC is the thermal diffusivity of the target fuel assembly, and dg is the grid height of the mixed core.

[0069] The embodiment of the application can accurately determine the critical heat flux density predicted value corresponding to the third critical heat flux density test point 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, thereby improving the efficiency and accuracy of determining the departure from nucleate boiling ratio design limit of the mixed core.

[0070] In an 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 predicted value corresponding to the fourth critical heat flux density test point as the departure from nucleate boiling ratio corresponding to the first critical heat flux density test point, the method for determining the departure from nucleate boiling ratio design limit of the mixed core provided by the embodiment of the application further comprises the following steps:

[0071] determining, for each first critical heat flux test point, a deviation of the first critical heat flux test point from a plurality of third critical heat flux test points;

[0072] determining, as a fourth critical heat flux test point, a third critical heat flux test point corresponding to a deviation within a preset range.

[0073] The embodiments of the present application can accurately determine, for each first critical heat flux test point, a fourth critical heat flux test point corresponding to the first critical heat flux test point from a plurality of third critical heat flux test points based on the deviation of the first critical heat flux test point from the plurality of third critical heat flux test points, and can further improve the accuracy of determining the departure from nucleate boiling ratio corresponding to the first critical heat flux test point based on a critical heat flux test value corresponding to the first critical heat flux test point and a critical heat flux prediction value corresponding to the fourth critical heat flux test point, thereby improving the efficiency and accuracy of determining the departure from nucleate boiling ratio design limit of the mixed core.

[0074] Optionally, the deviation of the first critical heat flux test point from the plurality of third critical heat flux test points includes at least one of:

[0075] a position deviation of the first position on the target fuel assembly from each second position;

[0076] a deviation of the same thermal parameter of the first critical heat flux test point from each third critical heat flux test point;

[0077] Optionally, the first position is a position on the target fuel assembly corresponding to the first critical heat flux test point at which the critical heat flux phenomenon occurs, and the second position is a position on the target fuel assembly corresponding to the third critical heat flux test point at which the critical heat flux phenomenon occurs.

[0078] Optionally, the target range and the preset range can be the same range or different ranges.

[0079] Optionally, the preset range includes at least one of:

[0080] -10 cm ≤ position deviation ≤ 10 cm;

[0081] -10% ≤ deviation of the same thermal parameter ≤ 10%.

[0082] Optionally, in the case where the thermal parameter includes temperature, pressure, flow rate, and gas content, the condition -10% ≤ deviation of the same thermal parameter ≤ 10% must be met simultaneously:

[0083] -10% ≤ deviation of temperature ≤ 10%;

[0084] -10% ≤ deviation of pressure ≤ 10%.

[0085] -10% < deviation of flow rate < 10%;

[0086] -10% < deviation of gas holdup < 10%.

[0087] The embodiment of the application can accurately determine the fourth critical heat flux density test point corresponding to the first critical heat flux density test point in the plurality of third critical heat flux density test points based on the position deviation of the first position on the target fuel assembly and each second position and / or the deviation of the same thermal parameter of the first critical heat flux density test point and each third critical heat flux density test point, and can further improve the accuracy of determining the deviation of the nucleate 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, thereby improving the efficiency and accuracy of determining the design limit value of the deviation of the nucleate boiling ratio of the mixed core.

[0088] Please refer to Figure 3 The embodiment of the application also provides a determination system (DNBR determination system) 300 for a design limit value of a deviation of a nucleate boiling ratio of a mixed core, which can implement the determination method for the design limit value of the deviation of the nucleate boiling ratio of the mixed core. The mixed core includes at least two fuel assemblies, and the full core of the mixed core is composed of a first fuel assembly in the at least two fuel assemblies. The system includes an acquisition module 301, a fuel assembly determination module 302, and a design limit value determination module 303.

[0089] The acquisition module 301 is configured to acquire a first design limit value of a deviation of a nucleate boiling ratio of the full core.

[0090] The fuel assembly determination module 302 is configured to determine a target fuel assembly in the at least two fuel assemblies. The deviation of the nucleate boiling ratio of the target fuel assembly represents the minimum deviation of the nucleate boiling ratio of the mixed core.

[0091] The design limit value determination module 303 is configured to determine the design limit value of the deviation of the nucleate boiling ratio of the mixed core according to the relationship between the deviation of the nucleate boiling ratio of the target fuel assembly and the first design limit value of the deviation of the nucleate boiling ratio.

[0092] The determination system for the design limit value of the deviation of the nucleate boiling ratio of the mixed core provided by the embodiment of the application can implement each step of the determination method for the design limit value of the deviation of the nucleate boiling ratio of the mixed core provided by the embodiment of the application, and can achieve the same technical effects. To avoid repetition, details are not described herein.

[0093] Optionally, as Figure 4As shown, the electronic device 400 in the embodiments of the present application includes a processor 401 and a memory 402, and the memory 402 stores programs or instructions executable on the processor 401, which, when executed by the processor 401, implement each step of the method for determining the mixed core deviation nucleate boiling ratio design limit in the embodiments of the present application and achieve the same technical effects. To avoid repetition, details are not described herein. It should be noted that the electronic device in the embodiments of the present application includes the mobile electronic device and the non-mobile electronic device described above.

[0094] Figure 5 To realize the hardware structure of the electronic device in the embodiments of the present application, the electronic device includes:

[0095] The processor 501 can be implemented in the form of a general-purpose CPU (Central Processing Unit), a microprocessor, an ASIC (Application Specific Integrated Circuit), or one or more integrated circuits, and is used to execute related programs to implement the technical solutions provided by the embodiments of the present application.

[0096] The memory 502 can be implemented in the form of a ROM (ReadOnly Memory), a static storage device, a dynamic storage device, or a RAM (Random Access Memory). The memory 502 can store an operating system and other application programs. When the technical solutions provided by the embodiments of the present application are implemented by software or firmware, the related program codes are stored in the memory 502 and are called and executed by the processor 501 to implement the method for determining the mixed core deviation nucleate boiling ratio design limit in the embodiments of the present application.

[0097] The input / output interface 503 is used to realize information input and output.

[0098] The communication interface 504 is used to realize the communication interaction between the device and other devices. The communication can be realized in a wired manner (for example, USB, network cable, etc.) or in a wireless manner (for example, mobile network, WIFI, Bluetooth, etc.).

[0099] The bus 505 transmits information between various components (for example, the processor 501, the memory 502, the input / output interface 503, and the communication interface 504) of the device.

[0100] The processor 501, the memory 502, the input / output interface 503, and the communication interface 504 are connected to each other in the device through the bus 505.

[0101] The electronic device provided by the embodiments of the present application can implement each step of the method for determining the mixed core deviation from the design limit of the nucleate boiling ratio, and achieve the same technical effects. To avoid repetition, the same will not be repeated here.

[0102] The embodiments of the present application also provide a computer readable storage medium, and the computer readable storage medium stores programs or instructions. When the programs or instructions are executed by a processor, each step of the method for determining the mixed core deviation from the design limit of the nucleate boiling ratio is implemented, and the same technical effects can be achieved. To avoid repetition, the same will not be repeated here.

[0103] 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 readable only memory (ROM), random access memory (RAM), magnetic disk or optical disk, etc.

[0104] The embodiments of the present application further provide a chip, and the chip includes a processor and a communication interface. The communication interface is coupled to the processor. The processor is configured to execute programs or instructions to implement each step of the method for determining the mixed core deviation from the design limit of the nucleate boiling ratio, and achieve the same technical effects. To avoid repetition, the same will not be repeated here.

[0105] It should be understood that the chip mentioned in the embodiments of the present application can also be referred to as a system-level chip, a system chip, a chip system, or a system-on-chip chip, etc.

[0106] The embodiments of the present application provide a computer program product stored in a storage medium. The program product is executed by at least one processor to implement each step of the method for determining the mixed core deviation from the design limit of the nucleate boiling ratio, and achieve the same technical effects. To avoid repetition, the same will not be repeated here.

[0107] It should be noted that, in the present document, the terms "comprises", "comprising", or any other variations thereof, are intended to cover a non-exclusive inclusion, such that a process, method, article, or apparatus that comprises a list of elements does not include only those elements but can include other elements not expressly listed or inherent to such process, method, article, or apparatus. An element proceeded by "comprises... a" does not, without more constraints, exclude the presence of additional identical elements in the process, method, article, or apparatus that comprises the element. Furthermore, it is to be understood that the method and apparatus of the present application can be carried out by more than one process, method, article, or apparatus either simultaneously, concurrently, or with intervening action that are carried out at the same time, either in a simultaneous fashion or in a fashion that is interleaved in time. For example, the described methods can be performed in a different order from that described, and / or various steps can be combined or omitted, and / or additional steps can be added, without departing from the scope of the present application. Also, features described with respect to certain examples can be combined in other examples.

[0108] From the above description of the embodiments, it is apparent that the above-mentioned method can be realized by means of software and necessary universal hardware platform, of course, it can also be realized by hardware, but in many cases, the former is a better embodiment. Based on such understanding, the technical solution of the present application can be embodied in the form of computer software product, which is stored in a storage medium (such as ROM / RAM, magnetic disk, optical disk), and includes a plurality of instructions for making a terminal (which can be a mobile phone, computer, server, or network equipment, etc.) execute the method described in various embodiments of the present application.

[0109] The embodiments of the present application are described above in conjunction with the drawings, but the present application is not limited to the above-described specific embodiments, and the above-described specific embodiments are merely illustrative, rather than limiting, and those skilled in the art can make many forms under the inspiration of the present application without departing from the scope of the present application and the scope protected by the claims.

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, including: 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 nucleus boiling ratio of the target fuel assembly characterizes the minimum deviation nucleus boiling ratio of the hybrid reactor core; 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; 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.

2. The determination method as described in claim 1, 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.

3. The determination method as described in claim 1, 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 matches 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.

4. The determination method as described in claim 3, 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.

5. 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.

6. 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 the target fuel assembly among the at least two fuel assemblies. The deviation nucleus boiling ratio of the target fuel assembly characterizes the minimum deviation nucleus boiling ratio of the hybrid reactor core. 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 design limit determination module is used to determine 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; The second critical heat flux density test point is the test point among the plurality of first critical heat flux density test points where the 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.

7. An electronic device, characterized in that, The electronic device includes a memory and a processor. The memory stores a computer program, and the processor executes the computer program to implement the method for determining the deviation of the hybrid core from the design limit of the core boiling ratio as described in any one of claims 1 to 5.

8. A computer-readable storage medium storing a computer program, characterized in that, When the computer program is executed by the processor, it implements the method for determining the deviation of the hybrid core from the design limit of the nucleation boiling ratio as described in any one of claims 1 to 5.

9. A computer program product, characterized in that, The computer program product is stored in a storage medium, and when executed by at least one processor, the computer program product implements the method for determining the deviation of the hybrid core from the design limit of the core boiling ratio as described in any one of claims 1 to 5.

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