Method and device for determining thermal margin of nuclear reactor, computer device and medium
By determining the first predicted deviation of the nucleus boiling ratio and component parameters of the reactor, the thermal margin is calculated, which solves the problem of insufficient accuracy of thermal margin in the prior art and realizes more accurate reactor safety analysis.
Patent Information
- Authority / Receiving Office
- CN · China
- Patent Type
- Patents(China)
- Current Assignee / Owner
- CHINA NUCLEAR POWER TECH RES INST CO LTD
- Filing Date
- 2023-11-29
- Publication Date
- 2026-05-01
AI Technical Summary
Existing technologies cannot accurately obtain the thermal margin of nuclear reactors, resulting in low accuracy in safety analysis of reactor operating conditions.
By determining the first predicted deviation nucleus boiling ratio of the reactor under test, and based on the reactor parameters at the predicted time, combined with axial and radial power, the thermal margin is calculated, taking into account the influence of each component, thereby improving the granularity and accuracy of the calculation.
This improves the accuracy of thermal margins, enabling them to better reflect the actual conditions of the reactor and enhancing the accuracy of safety analysis of reactor operating status.
Smart Images
Figure CN117766171B_ABST
Abstract
Description
Technical Field
[0001] This application relates to the field of nuclear engineering, and in particular to a method, apparatus, computer equipment, and medium for determining the thermal margin of a nuclear reactor. Background Technology
[0002] With the continuous development of nuclear engineering, in order to conduct safety analysis on the operating status of reactors, thermal margin analysis can be performed on the reactors to obtain the corresponding thermal margins; then, based on the values of the thermal margins, safety analysis of the reactors' operating status can be carried out.
[0003] Existing technologies can perform thermal margin analysis on reactors by analyzing the reactor core power distribution, thereby obtaining the corresponding thermal margin of the reactor. However, existing technologies cannot accurately obtain the thermal margin of the reactor, resulting in low accuracy in safety analysis of the reactor's operating status. Summary of the Invention
[0004] Therefore, it is necessary to provide a method, apparatus, computer equipment, and medium for determining the thermal margin of a nuclear reactor that can accurately obtain the thermal margin, in order to address the above-mentioned technical problems.
[0005] In a first aspect, this application provides a method for determining the thermal margin of a nuclear reactor. The method includes:
[0006] The first predicted deviation from the nucleus boiling ratio of the reactor under test is determined, wherein the first predicted deviation from the nucleus boiling ratio refers to the minimum predicted deviation from the nucleus boiling ratio of the reactor under test;
[0007] Based on the predicted time corresponding to the first predicted deviation from the nucleus boiling ratio, the reactor parameters of the reactor under test at the predicted time are determined. The reactor parameters include the axial power distribution and total power of at least one reactor component in the reactor under test. The total power of the component refers to the sum of the axial power and the radial power of the reactor component.
[0008] Based on the reactor parameters, determine the thermal margin of the reactor to be tested.
[0009] In one embodiment, determining the thermal margin of the reactor under test based on reactor parameters includes:
[0010] Based on the reactor parameters, the target deviation from the nucleus boiling ratio is determined, where the target deviation from the nucleus boiling ratio refers to the actual minimum deviation from the nucleus boiling ratio of the reactor under test.
[0011] The thermal margin of the reactor to be tested is determined based on the target deviation from the nucleus boiling ratio.
[0012] In one embodiment, determining the thermal margin of the reactor under test based on the target deviation from the nucleus-boiling ratio includes:
[0013] The thermal margin of the reactor under test is obtained by calculating the difference between the target deviation nucleus boiling ratio and the preset deviation nucleus boiling ratio.
[0014] In one embodiment, determining the target deviation from the nucleus boiling ratio based on reactor parameters includes:
[0015] Based on reactor parameters, determine the candidate deviation nucleus boiling ratio corresponding to at least one core channel;
[0016] The candidate deviation nucleus boiling ratio with the smallest value among the candidate deviation nucleus boiling ratios corresponding to each core channel is taken as the target deviation nucleus boiling ratio.
[0017] In one embodiment, determining a first predicted deviation from the nucleus boiling ratio of the reactor under test includes:
[0018] The target operating condition is determined from the candidate operating conditions corresponding to the reactor under test, and the core parameters of the target operating condition are determined.
[0019] Based on the core parameters, the deviation from the nucleus boiling ratio of the reactor under test is predicted, and the first predicted deviation from the nucleus boiling ratio of the reactor under test is obtained.
[0020] In one embodiment, based on the predicted time corresponding to the first predicted deviation from the nucleus boiling ratio, the reactor parameters of the reactor under test at the predicted time are determined, including:
[0021] Based on the predicted time corresponding to the first predicted deviation from the nucleus boiling ratio, the core physics library of the reactor to be tested is filtered to obtain the reactor parameters of the reactor to be tested at the predicted time.
[0022] Secondly, this application also provides a device for determining the thermal margin of a nuclear reactor. The device includes:
[0023] The first determining module is used to determine the first predicted deviation from the nucleus boiling ratio of the reactor under test, wherein the first predicted deviation from the nucleus boiling ratio refers to the minimum predicted deviation from the nucleus boiling ratio of the reactor under test.
[0024] The second determining module is used to determine the reactor parameters of the reactor under test at the predicted time based on the predicted time corresponding to the first predicted deviation from the nucleus boiling ratio. The reactor parameters include the axial power distribution and total power of at least one reactor component in the reactor under test. The total power of the component refers to the sum of the axial power and the radial power of the reactor component.
[0025] The third determination module is used to determine the thermal margin of the reactor under test based on the reactor parameters.
[0026] Thirdly, this application also provides a computer device. The computer device includes a memory and a processor, the memory storing a computer program, and the processor executing the computer program to perform the following steps:
[0027] The first predicted deviation from the nucleus boiling ratio of the reactor under test is determined, wherein the first predicted deviation from the nucleus boiling ratio refers to the minimum predicted deviation from the nucleus boiling ratio of the reactor under test;
[0028] Based on the predicted time corresponding to the first predicted deviation from the nucleus boiling ratio, the reactor parameters of the reactor under test at the predicted time are determined. The reactor parameters include the axial power distribution and total power of at least one reactor component in the reactor under test. The total power of the component refers to the sum of the axial power and the radial power of the reactor component.
[0029] Based on the reactor parameters, determine the thermal margin of the reactor to be tested.
[0030] Fourthly, this application also provides a computer-readable storage medium. The computer-readable storage medium stores a computer program thereon, which, when executed by a processor, performs the following steps:
[0031] The first predicted deviation from the nucleus boiling ratio of the reactor under test is determined, wherein the first predicted deviation from the nucleus boiling ratio refers to the minimum predicted deviation from the nucleus boiling ratio of the reactor under test;
[0032] Based on the predicted time corresponding to the first predicted deviation from the nucleus boiling ratio, the reactor parameters of the reactor under test at the predicted time are determined. The reactor parameters include the axial power distribution and total power of at least one reactor component in the reactor under test. The total power of the component refers to the sum of the axial power and the radial power of the reactor component.
[0033] Based on the reactor parameters, determine the thermal margin of the reactor to be tested.
[0034] Fifthly, this application also provides a computer program product. The computer program product includes a computer program that, when executed by a processor, performs the following steps:
[0035] The first predicted deviation from the nucleus boiling ratio of the reactor under test is determined, wherein the first predicted deviation from the nucleus boiling ratio refers to the minimum predicted deviation from the nucleus boiling ratio of the reactor under test;
[0036] Based on the predicted time corresponding to the first predicted deviation from the nucleus boiling ratio, the reactor parameters of the reactor under test at the predicted time are determined. The reactor parameters include the axial power distribution and total power of at least one reactor component in the reactor under test. The total power of the component refers to the sum of the axial power and the radial power of the reactor component.
[0037] Based on the reactor parameters, determine the thermal margin of the reactor to be tested.
[0038] The aforementioned method, apparatus, computer equipment, and medium for determining the thermal margin of a nuclear reactor determine the reactor parameters of the reactor under test at the predicted time of the first predicted deviation from the core boiling ratio. Further, based on the reactor parameters, the thermal margin of the reactor under test is determined. Since the reactor parameters in the above process include the axial power distribution and total power of at least one reactor component in the reactor under test, and the total power of the component refers to the sum of the axial and radial power of the reactor component, this application, compared to the prior art which only determines the thermal margin based on the core power distribution, considers the influence of the axial and radial power of each component on the determination of the thermal margin. Therefore, this application considers the factors affecting the thermal margin more comprehensively, has a finer calculation granularity, improves the accuracy of the thermal margin, and enables the thermal margin to more accurately reflect the actual situation of the reactor under test. Attached Figure Description
[0039] Figure 1 An application environment diagram for a method for determining the thermal margin of a nuclear reactor provided in this application embodiment;
[0040] Figure 2 A flowchart illustrating a method for determining the thermal margin of a nuclear reactor, provided as an embodiment of this application;
[0041] Figure 3 A flowchart illustrating the steps for determining the thermal margin of a reactor to be tested, as provided in this application embodiment;
[0042] Figure 4 A flowchart illustrating the steps for determining the target deviation from the nucleation-boiling ratio is provided in this application embodiment.
[0043] Figure 5 A flowchart illustrating the steps for determining a first predicted deviation from the nucleation-boiling ratio provided in this application embodiment;
[0044] Figure 6 A flowchart of another method for determining the thermal margin of a nuclear reactor provided in an embodiment of this application;
[0045] Figure 7 Structural block diagram of a first type of nuclear reactor thermal margin determination device provided in the embodiments of this application;
[0046] Figure 8 A structural block diagram of a second type of nuclear reactor thermal margin determination device provided in this application embodiment;
[0047] Figure 9 Structural block diagram of the third type of nuclear reactor thermal margin determination device provided in the embodiments of this application;
[0048] Figure 10 Structural block diagram of the fourth type of nuclear reactor thermal margin determination device provided in the embodiments of this application;
[0049] Figure 11 This is an internal structural diagram of a computer device in one embodiment. Detailed Implementation
[0050] To make the objectives, technical solutions, and advantages of this application clearer, the following detailed description is provided in conjunction with the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative and not intended to limit the scope of this application.
[0051] It should be understood that the specific embodiments described herein are merely illustrative of this application and are not intended to limit this application. In the description of this application, references to terms such as "one embodiment," "some embodiments," "example," "specific example," or "some examples," etc., indicate that a specific feature, structure, material, or characteristic described in connection with that embodiment or example is included in at least one embodiment or example of this application. In this specification, the illustrative expressions of the above terms do not necessarily refer to the same embodiment or example. Furthermore, the specific features, structures, materials, or characteristics described may be combined in a suitable manner in any one or more embodiments or examples. Moreover, without contradiction, those skilled in the art can combine and integrate the different embodiments or examples described in this specification, as well as the features of different embodiments or examples.
[0052] Based on the above, the method for determining the thermal margin of a nuclear reactor provided in this application can be applied to, for example... Figure 1 In the application environment shown, in one embodiment, a computer device is provided, which may be a server, and its internal structure diagram may be as follows. Figure 1As shown, the computer device includes a processor, memory, and a network interface connected via a system bus. The processor provides computational and control capabilities. The memory includes non-volatile storage media and internal memory. The non-volatile storage media stores the operating system, computer programs, and data blocks. The internal memory provides an environment for the operation of the operating system and computer programs in the non-volatile storage media. The data blocks store data acquired using a method for determining the thermal margin of a nuclear reactor. The network interface communicates with external terminals via a network connection. When executed by the processor, the computer program implements a method for determining the thermal margin of a nuclear reactor.
[0053] This application discloses a method, apparatus, computer equipment, and medium for determining thermal margin. By determining the first predicted deviation of the nucleus boiling ratio of the reactor under test, and based on the predicted time corresponding to the first predicted deviation of the nucleus boiling ratio, the reactor parameters of the reactor under test at the predicted time are determined, and the thermal margin of the reactor under test is determined based on the reactor parameters.
[0054] In one exemplary embodiment, such as Figure 2 As shown, Figure 2 This application provides a flowchart of a method for determining the thermal margin of a nuclear reactor, which is applied to... Figure 1 The following steps, 201 to 203, are used as an example of computer equipment.
[0055] Step 201: Determine the first predicted deviation nucleus boiling ratio of the reactor to be tested.
[0056] The first predicted deviation from the nucleus boiling ratio refers to the minimum predicted deviation from the nucleus boiling ratio of the reactor under test.
[0057] It should be noted that the first predicted deviation from the nucleus boiling ratio of the reactor under test can be determined by a pre-trained deviation nucleus boiling ratio prediction model.
[0058] Specifically, when it is necessary to determine the first predicted deviation from the nucleus boiling ratio of the reactor under test, the core parameters of the reactor under test under each candidate operating condition can be input into the deviation from the nucleus boiling ratio prediction model, and the output result of the deviation from the nucleus boiling ratio prediction model can be obtained. The output result is the first predicted deviation from the nucleus boiling ratio predicted by the deviation from the nucleus boiling ratio prediction model.
[0059] The training process of the deviation from the bubble-nucleus boiling ratio prediction model includes: obtaining sample parameters under sample operating conditions, and having staff mark the sample parameters with the first predicted deviation from the bubble-nucleus boiling ratio. The deviation from the bubble-nucleus boiling ratio prediction model is trained based on the sample parameters marked with the first predicted deviation from the bubble-nucleus boiling ratio, and the trained deviation from the bubble-nucleus boiling ratio prediction model is obtained.
[0060] To further explain, when it is necessary to determine the first predicted deviation from nucleus boiling ratio of the reactor core under test, the target operating condition when an accident occurs can be selected from the candidate operating conditions of the reactor core under test. Then, the core parameters under the target operating condition can be obtained to determine the critical deviation from nucleus boiling heat flux density and the actual heat flux density. The ratio of the critical deviation from nucleus boiling heat flux density to the actual heat flux density is used as the first predicted deviation from nucleus boiling ratio.
[0061] Step 202: Determine the reactor parameters of the reactor to be tested at the predicted time based on the predicted time corresponding to the first predicted deviation from the nucleus boiling ratio.
[0062] The reactor parameters include the axial power distribution and total power of at least one reactor component in the reactor under test. The total power of the component refers to the sum of the axial power and the radial power of the reactor component.
[0063] It should be noted that when it is necessary to determine the reactor parameters of the reactor to be tested at the predicted time, the following can be included: according to the predicted time corresponding to the first predicted deviation from the nucleus boiling ratio, the core physics library of the reactor to be tested is filtered to obtain the reactor parameters of the reactor to be tested at the predicted time, which are the axial power distribution and total power of at least one reactor component in the reactor to be tested.
[0064] To further clarify, when it is necessary to filter the core physics library of the reactor to be tested, the reactor parameters of the reactor to be tested at the predicted time can be obtained through keyword filtering, numerical filtering, category filtering, etc. Here, there is no limitation on the method of filtering the core physics library of the reactor to be tested.
[0065] In one embodiment of this application, to further improve the accuracy of thermal margin, the reactor parameters may further include the radial power distribution of at least one reactor component in the reactor under test, so that the influence of the radial power distribution of each reactor component on the thermal margin is considered in the subsequent process of determining the thermal margin based on the reactor parameters. Accordingly, when it is necessary to determine the reactor parameters of the reactor under test at the prediction time, the following may be included: according to the prediction time corresponding to the first prediction deviation from the nucleus boiling ratio, the core physics library of the reactor under test is filtered to obtain the reactor parameters of the reactor under test at the prediction time, which are the axial power distribution, radial power distribution and total power of at least one reactor component in the reactor under test.
[0066] Step 203: Determine the thermal margin of the reactor to be tested based on the reactor parameters.
[0067] Thermal margin refers to the margin by which the reactor under test can maintain operation, and is used to represent the safety performance of the reactor under test. Furthermore, the lower the thermal margin, the worse the safety and thermal performance of the reactor under test, and the higher the thermal margin, the better the safety and thermal performance of the reactor under test.
[0068] It should be noted that since the first predicted deviation from the nucleus boiling ratio refers to the predicted minimum deviation from the nucleus boiling ratio of the reactor under test, the thermal margin of the reactor under test cannot be accurately determined based on the first predicted deviation from the nucleus boiling ratio. Therefore, the target deviation from the nucleus boiling ratio of the reactor under test can be determined based on the reactor parameters corresponding to the first predicted deviation from the nucleus boiling ratio. The target deviation from the nucleus boiling ratio refers to the actual minimum deviation from the nucleus boiling ratio of the reactor under test. Therefore, when it is necessary to determine the thermal margin of the reactor under test, the following can be included: determine the target deviation from the nucleus boiling ratio based on the reactor parameters, and then determine the thermal margin of the reactor under test based on the target deviation from the nucleus boiling ratio.
[0069] In one embodiment of this application, candidate deviation nucleus boiling ratios corresponding to at least one core channel can be determined based on reactor parameters (i.e., the axial power distribution and total power of at least one reactor component in the reactor to be tested). The candidate deviation nucleus boiling ratio with the smallest value among the candidate deviation nucleus boiling ratios corresponding to each core channel is taken as the target deviation nucleus boiling ratio. Furthermore, the difference between the target deviation nucleus boiling ratio and the preset deviation nucleus boiling ratio is calculated to obtain the thermal margin of the reactor to be tested.
[0070] Specifically, reactor parameters can be input into a pre-trained first analysis model to obtain the output of the first analysis model, which is the candidate deviation bubble-nucleus boiling ratio corresponding to at least one core channel; furthermore, the first analysis model can be trained based on sample reactor parameters and the sample deviation bubble-nucleus boiling ratio corresponding to the sample reactor parameters.
[0071] To further improve the accuracy of determining the target deviation from the nucleus-boiling ratio, the influence of core parameters on the determination of the target deviation from the nucleus-boiling ratio can be considered during the process. Therefore, when it is necessary to determine the thermal margin of the reactor under test, the following can be included: determine the target deviation from the nucleus-boiling ratio based on the reactor parameters and core parameters, and then determine the thermal margin of the reactor under test based on the target deviation from the nucleus-boiling ratio.
[0072] In one embodiment of this application, candidate deviation nucleus boiling ratios corresponding to at least one core channel can be determined based on reactor parameters (i.e., the axial power distribution and total power of at least one reactor component in the reactor under test) and core parameters (e.g., core inlet temperature, pressure, flow rate, power, etc.). The candidate deviation nucleus boiling ratio with the smallest value among the candidate deviation nucleus boiling ratios corresponding to each core channel is taken as the target deviation nucleus boiling ratio. Furthermore, the difference between the target deviation nucleus boiling ratio and the preset deviation nucleus boiling ratio is calculated to obtain the thermal margin of the reactor under test.
[0073] Specifically, reactor parameters and core parameters can be input into a pre-trained second analysis model to obtain the output of the second analysis model, which is the candidate deviation bubble-nucleus boiling ratio corresponding to at least one core channel; furthermore, the second analysis model can be trained based on sample reactor parameters, sample core parameters, and sample deviation bubble-nucleus boiling ratios corresponding to the sample reactor parameters.
[0074] The aforementioned method for determining the thermal margin of a nuclear reactor determines the reactor parameters of the reactor under test at the predicted time of the first predicted deviation from the core boiling ratio. Further, based on these parameters, the thermal margin of the reactor under test is determined. Since the reactor parameters in this process include the axial power distribution and total power of at least one reactor component in the reactor under test, and the total power of the component refers to the sum of the axial and radial power of the reactor component, this application, compared to the prior art which only determines the thermal margin based on the core power distribution, considers the influence of the axial and radial power of each component on the determination of the thermal margin. Therefore, this application considers the factors affecting the thermal margin more comprehensively, has a finer calculation granularity, and improves the accuracy of the thermal margin, enabling it to more accurately reflect the actual situation of the reactor under test.
[0075] To ensure reactor safety, existing technologies calculate reactor thermal margins based on core power distribution, which suffers from low accuracy. To address this issue, the computer equipment described in this application can... Figure 3 The thermal margin of the reactor under test is determined in the manner shown, including steps 301 and 302. Wherein:
[0076] Step 301: Determine the target deviation nucleus boiling ratio based on reactor parameters.
[0077] Among them, the target deviation nucleus boiling ratio refers to the actual minimum deviation nucleus boiling ratio of the reactor under test.
[0078] In one embodiment of this application, if the reactor parameters are the axial power distribution and total power of at least one reactor component in the reactor to be tested, when it is necessary to determine the target deviation from the nucleus-boiling ratio, the following can be included: inputting the axial power distribution and total power of at least one reactor component in the reactor to be tested into the reactor calculation model X, and obtaining the output result of the reactor calculation model X, which is the target deviation from the nucleus-boiling ratio.
[0079] To further explain, the training process of reactor computation model X may include the following: setting the axial power distribution of sample reactor components, the total power of sample components, and the target deviation from the bubble-nucleus boiling ratio of sample reactor components; inputting the axial power distribution of sample reactor components, the total power of sample components, and the target deviation from the bubble-nucleus boiling ratio of sample reactor components into reactor computation model X; training reactor computation model X to obtain the trained reactor computation model X.
[0080] In another embodiment of this application, if the reactor parameters are the axial power distribution, radial power distribution, and total power of at least one reactor component in the reactor to be tested, when it is necessary to determine the target deviation from the nucleus-boiling ratio, the following can be included: inputting the radial power distribution and total power of at least one reactor component in the reactor to be tested into the reactor calculation model Y, and obtaining the output result of the reactor calculation model Y, which is the target deviation from the nucleus-boiling ratio.
[0081] To further explain, the training process of the reactor computation model Y may include the following: setting the axial power distribution, radial power distribution, total power of the sample reactor components, and target deviation from the bubble-nucleus boiling ratio of the sample reactor components; inputting the axial power distribution, radial power distribution, total power, and target deviation from the bubble-nucleus boiling ratio of the sample reactor components into the reactor computation model Y; and training the reactor computation model Y to obtain the trained reactor computation model Y.
[0082] Step 302: Determine the thermal margin of the reactor to be tested based on the target deviation from the nucleus boiling ratio.
[0083] It should be noted that when it is necessary to determine the thermal margin of the reactor to be tested, the following can be included: calculate the difference between the target deviation nucleus boiling ratio and the preset deviation nucleus boiling ratio to obtain the thermal margin of the reactor to be tested.
[0084] The preset deviation nucleus boiling ratio is determined based on the staff's historical work experience and the actual situation of the reactor.
[0085] In one embodiment of this application, if the target deviation from the nucleus boiling ratio is A, and the preset deviation from the nucleus boiling ratio is B, the difference between the target deviation from the nucleus boiling ratio and the preset deviation from the nucleus boiling ratio is calculated, and the result is AB, which is the thermal margin of the reactor to be tested.
[0086] The above-mentioned method for determining the thermal margin of a nuclear reactor takes into account the influence of axial power and radial power included in the reactor parameters on the determination of the thermal margin. This method considers the factors affecting the thermal margin more comprehensively, has a finer calculation granularity, and improves the accuracy of the thermal margin, so that the thermal margin can more accurately reflect the actual situation of the reactor under test.
[0087] In an exemplary embodiment, when it is necessary to determine the target deviation from the nucleus-boiling ratio based on reactor parameters, it can be done as follows: Figure 4 The method shown includes steps 401 and 402. Wherein:
[0088] Step 401: Based on the reactor parameters, determine the candidate deviation nucleus boiling ratio corresponding to at least one core channel.
[0089] Among them, the candidate deviated nucleus boiling ratio refers to the deviated nucleus boiling ratio corresponding to different core channels.
[0090] It should be noted that since the reactor under test is composed of multiple components, in order to ensure that the target deviation nucleus boiling ratio can more accurately reflect the true situation of the reactor under test, the multiple components contained in the reactor under test need to be divided into at least one core channel, and then the candidate deviation nucleus boiling ratio corresponding to each core channel needs to be determined.
[0091] In one embodiment of this application, when it is necessary to determine the candidate deviation nucleus boiling ratio corresponding to at least one core channel, the following may be included: inputting reactor parameters into the core channel model, dividing and calculating the reactor to be tested through the core channel model, and obtaining the output result of the core channel model, which is the candidate deviation nucleus boiling ratio corresponding to at least one core channel.
[0092] Further explanation, the training process of the core channel model may include the following: setting sample reactor parameters and sample candidate departure from nucleate boiling ratios, inputting the sample reactor parameters and sample candidate departure from nucleate boiling ratios into the core channel model, and training the core channel model to obtain the trained core channel model.
[0093] Step 402: Take the candidate departure from nucleate boiling ratio with the minimum value among the candidate departure from nucleate boiling ratios corresponding to each core channel as the target departure from nucleate boiling ratio.
[0094] It should be noted that when determining the target departure from nucleate boiling ratio, it is necessary to sort the candidate departure from nucleate boiling ratios corresponding to each core channel from small to large. The candidate departure from nucleate boiling ratio ranked first after sorting is the one with the minimum value among the candidate departure from nucleate boiling ratios corresponding to each core channel. Take this candidate departure from nucleate boiling ratio as the target departure from nucleate boiling ratio.
[0095] For example, if the value of the first candidate departure from nucleate boiling ratio is a, the value of the second candidate departure from nucleate boiling ratio is b, and the value of the third candidate departure from nucleate boiling ratio is c, where b < a < c. Since the value of the second candidate departure from nucleate boiling ratio is the smallest, the second candidate departure from nucleate boiling ratio is taken as the target departure from nucleate boiling ratio.
[0096] The above method for determining the thermal margin of a nuclear reactor obtains the candidate departure from nucleate boiling ratios corresponding to at least one core channel through reactor parameters, and selects the candidate heat flux density with the minimum value as the target departure from nucleate boiling ratio, providing a calculation basis for subsequent determination of the thermal margin of the reactor to be detected.
[0097] In an exemplary embodiment, when it is necessary to determine the first predicted departure from nucleate boiling ratio of the reactor to be detected, it can be done in the following manner shown in Figure 5 and includes the following steps 501 and step 502. Where:
[0098] Step 501: Determine the target operating condition from the candidate operating conditions corresponding to the reactor to be detected, and determine the core parameters of the target operating condition.
[0099] Among them, candidate operating condition refers to any operating condition that the reactor under test may experience during operation; target operating condition refers to the operating condition of the reactor under test when an accident occurs during operation, such as DBC1-2 (Design Basis Condition 1-2) type operating condition, DBC3-4 (Design Basis Condition 3-4) type operating condition, etc.; core parameters refer to the core thermal state parameters (e.g., core inlet temperature, pressure, flow rate, power, etc.) of the reactor under test at the time of accident initiation under the target operating condition, as well as the accident initiation event (e.g., rod drop accident).
[0100] It should be noted that when it is necessary to determine the target operating condition from the candidate operating conditions corresponding to the reactor to be tested, the candidate operating conditions corresponding to the reactor to be tested can be screened, and the operating condition of the reactor to be tested under the condition of an accident during operation can be selected from the candidate operating conditions, which is the target operating condition corresponding to the reactor to be tested.
[0101] In one embodiment of this application, when it is necessary to determine the target operating condition from the candidate operating conditions corresponding to the reactor under test, and to determine the core parameters of the target operating condition, the candidate operating conditions can be screened through the operating condition screening model to obtain the target operating condition. Furthermore, the reactor under test can be detected and analyzed by the detection equipment pre-set in the core under test to obtain the core parameters. The detection equipment may include temperature detection equipment, pressure detection equipment, flow detection equipment, etc.
[0102] To further explain, the training process of the working condition screening model may include the following: setting sample candidate working conditions and sample target working conditions, inputting the sample candidate working conditions and sample target working conditions into the working condition screening model, training the working condition screening model, and obtaining the trained working condition screening model.
[0103] Step 502: Based on the core parameters, predict the deviation from the nucleus boiling ratio of the reactor under test to obtain the first predicted deviation from the nucleus boiling ratio of the reactor under test.
[0104] In one embodiment of this application, when it is necessary to predict the deviation from the nucleus boiling ratio of the reactor under test based on the core parameters, so as to obtain the first predicted deviation from the nucleus boiling ratio of the reactor under test, the core parameters can be input into the core calculation model, and the reactor under test can be predicted and calculated through the core calculation model. The result of the core calculation model is the first predicted deviation from the nucleus boiling ratio of the reactor under test.
[0105] To further explain, the training process of the core computing model may include the following: setting the sample core parameters and the sample first predicted deviation from the bubble-nucleus boiling ratio, inputting the sample core parameters and the sample first predicted deviation from the bubble-nucleus boiling ratio into the core computing model, training the core computing model to obtain the trained core computing model.
[0106] The above-mentioned method for determining the thermal margin of a nuclear reactor predicts the deviation from the nucleus boiling ratio of the reactor under test by using the core parameters of the target operating condition. This yields the first predicted deviation from the nucleus boiling ratio of the reactor under test, providing a basis for subsequent determination of the thermal margin of the reactor under test.
[0107] In one embodiment of this application, when it is necessary to determine the reactor parameters of the reactor to be tested at the predicted time, the reactor core physics library of the reactor to be tested can be filtered according to the predicted time corresponding to the first predicted deviation from the nucleus boiling ratio to obtain the reactor parameters of the reactor to be tested at the predicted time.
[0108] The core physics library is used to store the physical characteristics of the reactor under test, such as component power distribution (including component axial power distribution and component radial power distribution), and total component power (the sum of the component's axial power and radial power).
[0109] The aforementioned method for determining the thermal margin of a nuclear reactor obtains the reactor parameters of the reactor under test at the predicted time from the reactor core physics library, thus providing a basis for subsequently determining the thermal margin of the reactor under test.
[0110] In an exemplary embodiment, when it is necessary to store each data block to be stored, the specific process may include the following steps: Figure 6 As shown:
[0111] Step 601: Determine the target operating condition from the candidate operating conditions corresponding to the reactor to be tested, and determine the core parameters of the target operating condition.
[0112] Step 602: Based on the core parameters, predict the deviation from the nucleus boiling ratio of the reactor under test to obtain the first predicted deviation from the nucleus boiling ratio of the reactor under test.
[0113] Step 603: Determine the reactor parameters of the reactor to be tested at the predicted time based on the predicted time corresponding to the first predicted deviation from the nucleus boiling ratio.
[0114] Step 604: Based on the reactor parameters, determine the candidate deviation nucleus boiling ratio corresponding to at least one core channel.
[0115] Step 605: Take the candidate deviation nucleus boiling ratio with the smallest value among the candidate deviation nucleus boiling ratios corresponding to each core channel as the target deviation nucleus boiling ratio.
[0116] Step 606: Perform a difference calculation between the target deviation nucleus boiling ratio and the preset deviation nucleus boiling ratio to obtain the thermal margin of the reactor to be tested.
[0117] The aforementioned method for determining the thermal margin of a nuclear reactor determines the reactor parameters of the reactor under test at the predicted time of the first predicted deviation from the core boiling ratio. Further, based on these parameters, the thermal margin of the reactor under test is determined. Since the reactor parameters in this process include the axial power distribution and total power of at least one reactor component in the reactor under test, and the total power of the component refers to the sum of the axial and radial power of the reactor component, this application, compared to the prior art which only determines the thermal margin based on the core power distribution, considers the influence of the axial and radial power of each component on the determination of the thermal margin. Therefore, this application considers the factors affecting the thermal margin more comprehensively, has a finer calculation granularity, and improves the accuracy of the thermal margin, enabling it to more accurately reflect the actual situation of the reactor under test.
[0118] It should be understood that although the steps in the flowcharts of the above embodiments are shown sequentially according to the arrows, these steps are not necessarily executed in the order indicated by the arrows. Unless explicitly stated herein, there is no strict order restriction on the execution of these steps, and they can be executed in other orders. Moreover, at least some steps in the flowcharts of the above embodiments may include multiple steps or multiple stages. These steps or stages are not necessarily completed at the same time, but can be executed at different times. The execution order of these steps or stages is not necessarily sequential, but can be performed alternately or in turn with other steps or at least some of the steps or stages of other steps.
[0119] Based on the same inventive concept, this application also provides a thermal margin determination apparatus for nuclear reactors to implement the above-described method for determining the thermal margin of nuclear reactors. The solution provided by this apparatus is similar to the solution described in the above-described method. Therefore, the specific limitations of one or more embodiments of the thermal margin determination apparatus for nuclear reactors provided below can be found in the limitations of the method for determining the thermal margin of nuclear reactors described above, and will not be repeated here.
[0120] In one embodiment, such as Figure 7 As shown, a device for determining the thermal margin of a nuclear reactor is provided, comprising: a first determining module 10, a second determining module 20, and a third determining module 30, wherein:
[0121] The first determining module 10 is used to determine the first predicted deviation nucleus boiling ratio of the reactor to be tested.
[0122] The second determining module 20 is used to determine the reactor parameters of the reactor under test at the predicted time based on the predicted time corresponding to the first predicted deviation from the nucleus boiling ratio. The reactor parameters include the axial power distribution and total power of at least one reactor component in the reactor under test. The total power of the component refers to the sum of the axial power and the radial power of the reactor component.
[0123] The second determining module 20 is specifically used to filter the core physics library of the reactor to be tested based on the predicted time corresponding to the first predicted deviation from the nucleus boiling ratio, and obtain the reactor parameters of the reactor to be tested at the predicted time.
[0124] The third determining module 30 is used to determine the thermal margin of the reactor to be tested based on the reactor parameters.
[0125] The aforementioned thermal margin determination device for nuclear reactors determines the reactor parameters of the reactor under test at the predicted time of the first predicted deviation from the core boiling ratio. Further, based on the reactor parameters, it determines the thermal margin of the reactor under test. Since the reactor parameters in the above process include the axial power distribution and total power of at least one reactor component in the reactor under test, and the total power of the component refers to the sum of the axial and radial power of the reactor component, this application, compared to the prior art which only determines the thermal margin based on the core power distribution, considers the influence of the axial and radial power of each component on the determination of the thermal margin. Therefore, this application considers the factors affecting the thermal margin more comprehensively, has a finer calculation granularity, improves the accuracy of the thermal margin, and enables the thermal margin to more accurately reflect the actual situation of the reactor under test.
[0126] In one embodiment, such as Figure 8 As shown, a device for determining the thermal margin of a nuclear reactor is provided. The third determining module 30 in this device includes: a first determining unit 31 and a second determining unit 32, wherein:
[0127] The first determining unit 31 is used to determine the target deviation from the nucleus boiling ratio based on the reactor parameters, wherein the target deviation from the nucleus boiling ratio refers to the actual minimum deviation from the nucleus boiling ratio of the reactor to be tested.
[0128] The second determining unit 32 is used to determine the thermal margin of the reactor to be tested based on the target deviation from the nucleus boiling ratio.
[0129] The second determining unit 32 is specifically used to perform difference calculation between the target deviation nucleus boiling ratio and the preset deviation nucleus boiling ratio to obtain the thermal margin of the reactor to be tested.
[0130] In one embodiment, such as Figure 9 As shown, a device for determining the thermal margin of a nuclear reactor is provided. The first determining unit 31 in this device includes: a first determining subunit 311 and a second determining subunit 312, wherein:
[0131] The first determining subunit 311 is used to determine, based on reactor parameters, a candidate deviation nucleus boiling ratio corresponding to at least one core channel.
[0132] The second determining subunit 312 is used to take the candidate deviation nucleus boiling ratio with the smallest value among the candidate deviation nucleus boiling ratios corresponding to each core channel as the target deviation nucleus boiling ratio.
[0133] In one embodiment, such as Figure 10 As shown, a device for determining the thermal margin of a nuclear reactor is provided. The first determining module 10 of this device includes a third determining unit 11 and a fourth determining unit 12, wherein:
[0134] The third determining unit 11 is used to determine the target operating condition from the candidate operating conditions corresponding to the reactor to be tested, and to determine the core parameters of the target operating condition.
[0135] The fourth determining unit 12 is used to predict the deviation from the nucleus boiling ratio of the reactor under test based on the core parameters, and to obtain the first predicted deviation from the nucleus boiling ratio of the reactor under test.
[0136] The modules in the aforementioned thermal margin determination device for nuclear reactors can be implemented entirely or partially through software, hardware, or a combination thereof. These modules can be embedded in or independent of the processor in a computer device, or stored in the memory of a computer device as software, so that the processor can call and execute the operations corresponding to each module.
[0137] In one embodiment, a computer device is provided, which may be a terminal, and its internal structure diagram may be as follows: Figure 11As shown, the computer device includes a processor, memory, input / output interface, communication interface, display unit, and input device. The processor, memory, and input / output interface are connected via a system bus, and the communication interface, display unit, and input device are also connected to the system bus via the input / output interface. The processor provides computing and control capabilities. The memory includes non-volatile storage media and internal memory. The non-volatile storage media stores the operating system and computer programs. The internal memory provides an environment for the operation of the operating system and computer programs in the non-volatile storage media. The input / output interface is used for exchanging information between the processor and external devices. The communication interface is used for wired or wireless communication with external terminals; wireless communication can be achieved through Wi-Fi, mobile cellular networks, NFC (Near Field Communication), or other technologies. When executed by the processor, the computer program implements a method for determining the thermal margin of a nuclear reactor. The display unit is used to form a visually visible image and can be a display screen, projection device, or virtual reality imaging device. The display screen can be an LCD screen or an e-ink screen. The input device of the computer device can be a touch layer covering the display screen, or buttons, trackballs, or touchpads set on the casing of the computer device, or external keyboards, touchpads, or mice, etc.
[0138] Those skilled in the art will understand that Figure 11 The structure shown is merely a block diagram of a portion of the structure related to the present application and does not constitute a limitation on the computer device to which the present application is applied. Specific computer devices may include more or fewer components than those shown in the figure, or combine certain components, or have different component arrangements.
[0139] In one embodiment, a computer device is provided, including a memory and a processor, wherein the memory stores a computer program, and the processor executes the computer program to perform the following steps:
[0140] The first predicted deviation from the nucleus boiling ratio of the reactor under test is determined, wherein the first predicted deviation from the nucleus boiling ratio refers to the minimum predicted deviation from the nucleus boiling ratio of the reactor under test;
[0141] Based on the predicted time corresponding to the first predicted deviation from the nucleus boiling ratio, the reactor parameters of the reactor under test at the predicted time are determined. The reactor parameters include the axial power distribution and total power of at least one reactor component in the reactor under test. The total power of the component refers to the sum of the axial power and the radial power of the reactor component.
[0142] Based on the reactor parameters, determine the thermal margin of the reactor to be tested.
[0143] In one embodiment, the processor, when executing a computer program, also performs the following steps:
[0144] Based on the reactor parameters, the target deviation from the nucleus boiling ratio is determined, where the target deviation from the nucleus boiling ratio refers to the actual minimum deviation from the nucleus boiling ratio of the reactor under test.
[0145] The thermal margin of the reactor to be tested is determined based on the target deviation from the nucleus boiling ratio.
[0146] In one embodiment, the processor, when executing a computer program, also performs the following steps:
[0147] The thermal margin of the reactor under test is obtained by calculating the difference between the target deviation nucleus boiling ratio and the preset deviation nucleus boiling ratio.
[0148] In one embodiment, the processor, when executing a computer program, also performs the following steps:
[0149] Based on reactor parameters, determine the candidate deviation nucleus boiling ratio corresponding to at least one core channel;
[0150] The candidate deviation nucleus boiling ratio with the smallest value among the candidate deviation nucleus boiling ratios corresponding to each core channel is taken as the target deviation nucleus boiling ratio.
[0151] In one embodiment, the processor, when executing a computer program, also performs the following steps:
[0152] The target operating condition is determined from the candidate operating conditions corresponding to the reactor under test, and the core parameters of the target operating condition are determined.
[0153] Based on the core parameters, the deviation from the nucleus boiling ratio of the reactor under test is predicted, and the first predicted deviation from the nucleus boiling ratio of the reactor under test is obtained.
[0154] In one embodiment, the processor, when executing a computer program, also performs the following steps:
[0155] Based on the predicted time corresponding to the first predicted deviation from the nucleus boiling ratio, the core physics library of the reactor to be tested is filtered to obtain the reactor parameters of the reactor to be tested at the predicted time.
[0156] In one embodiment, a computer-readable storage medium is provided having a computer program stored thereon, the computer program performing the following steps when executed by a processor:
[0157] The first predicted deviation from the nucleus boiling ratio of the reactor under test is determined, wherein the first predicted deviation from the nucleus boiling ratio refers to the minimum predicted deviation from the nucleus boiling ratio of the reactor under test;
[0158] Based on the predicted time corresponding to the first predicted deviation from the nucleus boiling ratio, the reactor parameters of the reactor under test at the predicted time are determined. The reactor parameters include the axial power distribution and total power of at least one reactor component in the reactor under test. The total power of the component refers to the sum of the axial power and the radial power of the reactor component.
[0159] Based on the reactor parameters, determine the thermal margin of the reactor to be tested.
[0160] In one embodiment, when the computer program is executed by a processor, it also performs the following steps:
[0161] Based on the reactor parameters, the target deviation from the nucleus boiling ratio is determined, where the target deviation from the nucleus boiling ratio refers to the actual minimum deviation from the nucleus boiling ratio of the reactor under test.
[0162] The thermal margin of the reactor to be tested is determined based on the target deviation from the nucleus boiling ratio.
[0163] In one embodiment, when the computer program is executed by a processor, it also performs the following steps:
[0164] The thermal margin of the reactor under test is obtained by calculating the difference between the target deviation nucleus boiling ratio and the preset deviation nucleus boiling ratio.
[0165] In one embodiment, when the computer program is executed by a processor, it also performs the following steps:
[0166] Based on reactor parameters, determine the candidate deviation nucleus boiling ratio corresponding to at least one core channel;
[0167] The candidate deviation nucleus boiling ratio with the smallest value among the candidate deviation nucleus boiling ratios corresponding to each core channel is taken as the target deviation nucleus boiling ratio.
[0168] In one embodiment, when the computer program is executed by a processor, it also performs the following steps:
[0169] The target operating condition is determined from the candidate operating conditions corresponding to the reactor under test, and the core parameters of the target operating condition are determined.
[0170] Based on the core parameters, the deviation from the nucleus boiling ratio of the reactor under test is predicted, and the first predicted deviation from the nucleus boiling ratio of the reactor under test is obtained.
[0171] In one embodiment, when the computer program is executed by a processor, it also performs the following steps:
[0172] Based on the predicted time corresponding to the first predicted deviation from the nucleus boiling ratio, the core physics library of the reactor to be tested is filtered to obtain the reactor parameters of the reactor to be tested at the predicted time.
[0173] In one embodiment, a computer program product is provided, including a computer program that, when executed by a processor, performs the following steps:
[0174] The first predicted deviation from the nucleus boiling ratio of the reactor under test is determined, wherein the first predicted deviation from the nucleus boiling ratio refers to the minimum predicted deviation from the nucleus boiling ratio of the reactor under test;
[0175] Based on the predicted time corresponding to the first predicted deviation from the nucleus boiling ratio, the reactor parameters of the reactor under test at the predicted time are determined. The reactor parameters include the axial power distribution and total power of at least one reactor component in the reactor under test. The total power of the component refers to the sum of the axial power and the radial power of the reactor component.
[0176] Based on the reactor parameters, determine the thermal margin of the reactor to be tested.
[0177] In one embodiment, when the computer program is executed by a processor, it also performs the following steps:
[0178] Based on the reactor parameters, the target deviation from the nucleus boiling ratio is determined, where the target deviation from the nucleus boiling ratio refers to the actual minimum deviation from the nucleus boiling ratio of the reactor under test.
[0179] The thermal margin of the reactor to be tested is determined based on the target deviation from the nucleus boiling ratio.
[0180] In one embodiment, when the computer program is executed by a processor, it also performs the following steps:
[0181] The thermal margin of the reactor under test is obtained by calculating the difference between the target deviation nucleus boiling ratio and the preset deviation nucleus boiling ratio.
[0182] In one embodiment, when the computer program is executed by a processor, it also performs the following steps:
[0183] Based on reactor parameters, determine the candidate deviation nucleus boiling ratio corresponding to at least one core channel;
[0184] The candidate deviation nucleus boiling ratio with the smallest value among the candidate deviation nucleus boiling ratios corresponding to each core channel is taken as the target deviation nucleus boiling ratio.
[0185] In one embodiment, when the computer program is executed by a processor, it also performs the following steps:
[0186] The target operating condition is determined from the candidate operating conditions corresponding to the reactor under test, and the core parameters of the target operating condition are determined.
[0187] Based on the core parameters, the deviation from the nucleus boiling ratio of the reactor under test is predicted, and the first predicted deviation from the nucleus boiling ratio of the reactor under test is obtained.
[0188] In one embodiment, when the computer program is executed by a processor, it also performs the following steps:
[0189] Based on the predicted time corresponding to the first predicted deviation from the nucleus boiling ratio, the core physics library of the reactor to be tested is filtered to obtain the reactor parameters of the reactor to be tested at the predicted time.
[0190] It should be noted that the user information (including but not limited to user device information, user personal information, etc.) and data (including but not limited to data used for analysis, data stored, data displayed, etc.) involved in this application are all information and data authorized by the user or fully authorized by all parties, and the collection, use and processing of related data must comply with the relevant laws, regulations and standards of the relevant countries and regions.
[0191] Those skilled in the art will understand that all or part of the processes in the above embodiments can be implemented by a computer program instructing related hardware. This computer program can be stored in a non-volatile computer-readable storage medium. When executed, the computer program can include the processes of the embodiments described above. Any references to memory, data blocks, or other media used in the embodiments provided in this application can include at least one of non-volatile and volatile memory. Non-volatile memory can include read-only memory (ROM), magnetic tape, floppy disk, flash memory, optical memory, high-density embedded non-volatile memory, resistive random access memory (ReRAM), magnetic random access memory (MRAM), ferroelectric random access memory (FRAM), phase change memory (PCM), graphene memory, etc. Volatile memory can include random access memory (RAM) or external cache memory, etc. By way of illustration and not limitation, RAM can take many forms, such as Static Random Access Memory (SRAM) or Dynamic Random Access Memory (DRAM). The data blocks involved in the embodiments provided in this application may include at least one of relational data blocks and non-relational data blocks. Non-relational data blocks may include, but are not limited to, blockchain-based distributed data blocks. The processors involved in the embodiments provided in this application may be general-purpose processors, central processing units, graphics processing units, digital signal processors, programmable logic devices, quantum computing-based data processing logic devices, etc., and are not limited to these.
[0192] The technical features of the above embodiments can be combined in any way. For the sake of brevity, not all possible combinations of the technical features in the above embodiments are described. However, as long as there is no contradiction in the combination of these technical features, they should be considered to be within the scope of this specification.
[0193] The above embodiments are merely illustrative of several implementation methods of this application, and their descriptions are relatively specific and detailed. However, they should not be construed as limiting the scope of this application. It should be noted that those skilled in the art can make various modifications and improvements without departing from the concept of this application, and these all fall within the protection scope of this application. Therefore, the protection scope of this application should be determined by the appended claims.
Claims
1. A method for determining the thermal margin of a nuclear reactor, characterized in that, The method includes: Determine the first predicted deviation from nucleus boiling ratio of the reactor under test, wherein the first predicted deviation from nucleus boiling ratio refers to the minimum predicted deviation from nucleus boiling ratio of the reactor under test; Based on the predicted time corresponding to the first predicted deviation from the nucleus boiling ratio, the reactor parameters of the reactor under test at the predicted time are determined. The reactor parameters include the axial power distribution and total power of at least one reactor component in the reactor under test. The total power of the component refers to the sum of the axial power and the radial power of the reactor component. Based on the reactor parameters, determine at least one candidate deviation nucleus boiling ratio corresponding to a core channel; The candidate deviation from the core boiling ratio with the smallest value among the candidate deviation from the core boiling ratio corresponding to each core channel is taken as the target deviation from the core boiling ratio. The thermal margin of the reactor under test is determined based on the target deviation from the nucleus boiling ratio.
2. The method according to claim 1, characterized in that, The step of determining the thermal margin of the reactor under test based on the target deviation from the nucleus-boiling ratio includes: The thermal margin of the reactor under test is obtained by performing a difference calculation between the target deviation nucleus boiling ratio and the preset deviation nucleus boiling ratio.
3. The method according to claim 1, characterized in that, The determination of the first predicted deviation from the nucleus boiling ratio of the reactor under test includes: The target operating condition is determined from the candidate operating conditions corresponding to the reactor under test, and the core parameters of the target operating condition are determined. Based on the core parameters, the deviation from the nucleus boiling ratio of the reactor under test is predicted to obtain the first predicted deviation from the nucleus boiling ratio of the reactor under test.
4. The method according to claim 1, characterized in that, The step of determining the reactor parameters of the reactor under test at the predicted time based on the predicted time corresponding to the first predicted deviation from the nucleus boiling ratio includes: Based on the predicted time corresponding to the first predicted deviation from the nucleus boiling ratio, the core physics library of the reactor under test is filtered to obtain the reactor parameters of the reactor under test at the predicted time.
5. The method according to claim 1, characterized in that, The step of determining the candidate deviation nucleus boiling ratio corresponding to at least one core channel based on the reactor parameters includes: Based on the reactor parameters and core parameters, determine at least one candidate deviation nucleus boiling ratio corresponding to a core channel; the core parameters refer to the core thermal state parameters of the reactor under test and the accident initiation event at the time of accident initiation under the target operating condition.
6. The method according to claim 1, characterized in that, The determination of the first predicted deviation from the nucleus boiling ratio of the reactor under test includes: The core parameters of the reactor under test under each candidate operating condition are input into the deviation from the bubble-nucleus boiling ratio prediction model, and the output result of the deviation from the bubble-nucleus boiling ratio prediction model is obtained. The output result is the first predicted deviation from the bubble-nucleus boiling ratio predicted by the deviation from the bubble-nucleus boiling ratio prediction model.
7. A device for determining the thermal margin of a nuclear reactor, characterized in that, The device includes: The first determining module is used to determine the first predicted deviation from the nucleus boiling ratio of the reactor under test, wherein the first predicted deviation from the nucleus boiling ratio refers to the minimum predicted deviation from the nucleus boiling ratio of the reactor under test. The second determining module is used to determine the reactor parameters of the reactor under test at the predicted time based on the predicted time corresponding to the first predicted deviation from the nucleus boiling ratio. The reactor parameters include the axial power distribution and total power of at least one reactor component in the reactor under test. The total power of the component refers to the sum of the axial power and the radial power of the reactor component. The third determining module is used to determine, based on the reactor parameters, at least one candidate deviation bubble nucleus boiling ratio corresponding to a core channel; take the candidate deviation bubble nucleus boiling ratio with the smallest value among the candidate deviation bubble nucleus boiling ratios corresponding to each core channel as the target deviation bubble nucleus boiling ratio; and determine the thermal margin of the reactor to be tested based on the target deviation bubble nucleus boiling ratio.
8. A computer device comprising a memory and a processor, wherein the memory stores a computer program, characterized in that, When the processor executes the computer program, it implements the steps of the method according to any one of claims 1 to 6.
9. A computer-readable storage medium having a computer program stored thereon, characterized in that, When the computer program is executed by a processor, it implements the steps of the method according to any one of claims 1 to 6.
10. A computer program product, comprising a computer program, characterized in that, When the computer program is executed by a processor, it implements the steps of the method according to any one of claims 1 to 6.