A digital visualized reactivity measurement method, apparatus, system and device

Abstract

The application discloses a digital visualized reactivity measurement method, device, system and equipment, and the method comprises the following steps: obtaining a digital neutron measurement signal by using a front-end digitization-based signal measurement method; establishing a three-dimensional physical analysis model by using a three-dimensional digital coordinate positioning-based digital modeling method; correcting the three-dimensional physical analysis model by using a three-dimensional calculation model optimization method based on a measured critical rod position to obtain a corrected calculation model; obtaining a correction factor based on the corrected calculation model, correcting the digital neutron measurement signal to obtain a corrected neutron detection signal; performing reactivity measurement based on the corrected neutron detection signal; and establishing a three-dimensional core visualized model based on the corrected calculation model, and displaying the reactivity measurement result in a numerical form on the three-dimensional core visualized model. The application realizes accurate and reliable digital visualized reactivity measurement, and provides a theoretical basis for efficient and accurate measurement of core reactivity physical parameters.

Description

Technical Field

[0001] This application relates to the field of nuclear reactor reactivity measurement technology, specifically to a digitally visualized reactivity measurement method, apparatus, system, and equipment. Background Technology

[0002] In current nuclear reactor research, critical physics experiments are required to measure key physical parameters such as reactivity. However, existing critical physics experiments typically employ a single measurement method for each parameter, resulting in long processing times and low efficiency. Furthermore, the measurement results from these experiments are generally abstract numerical values ​​with low or no visualization, making it impossible to intuitively and in real-time assess the results. Unsatisfactory results may necessitate repeating the experiment, restarting or shutting down the reactor, or even disassembling and reassembling the test reactor core, significantly increasing workload and limiting experimental efficiency and accuracy.

[0003] Extensive research has been conducted both domestically and internationally on methods for measuring reactive physical parameters, proposing advanced three-dimensional measurement methods such as inverse dynamic reactivity measurement methods based on three-dimensional spatiotemporal dynamics, and achieving good measurement results. However, due to the objective existence of measurement model biases, the measurement uncertainties of neutron signals and core geometry are difficult to completely eliminate, and there are differences between the actual core parameters and the calculated model. The accuracy of the three-dimensional correction calculation model has limitations, and the accuracy of measurement and three-dimensional correction remains restricted.

[0004] Currently, there are no reports on accurate digital visualization reactivity measurement technology in China. Therefore, it is urgent to study an independent and accurate digital visualization reactivity measurement method to address the differences between domestically developed reactor cores and foreign reactor cores, and to provide technical support for the efficient and accurate measurement of reactor core reactivity physical parameters. Summary of the Invention

[0005] To address the limitations of existing nuclear reactor reactivity measurement methods, such as low visualization levels and constraints on accuracy and precision due to biases in the measurement models, this application proposes a digitally visualized reactivity measurement method, apparatus, system, and equipment. This application employs a front-end digitized signal measurement method to measure digital neutron signals, improving the accuracy and reliability of the neutron measurement signals and providing a more accurate and reliable data foundation for subsequent analysis. Furthermore, it utilizes a modeling method based on the actual three-dimensional digital positioning coordinates of the reactor core to construct the physical calculation model, avoiding the problem of low accuracy in the physical calculation model caused by differences between actual and design parameters of the reactor core, thus improving the model's reliability and providing a more accurate and reliable calculation model for subsequent measurement and analysis. Finally, it uses a high-precision visualization model to digitally display the three-dimensional correction calculations of the reactivity measurement results, facilitating intuitive and real-time evaluation of the results and ensuring experimental efficiency and accuracy.

[0006] This application is achieved through the following technical solution:

[0007] A digitally visualized method for measuring reactivity, the method comprising:

[0008] Digital neutron measurement signals were obtained using a front-end digitization-based signal measurement method.

[0009] A three-dimensional physical analysis model is established using a digital modeling method based on three-dimensional digital coordinate positioning.

[0010] The three-dimensional physical analysis model is modified by using a three-dimensional calculation model optimization method based on measured critical rod positions to obtain a modified calculation model;

[0011] Based on the aforementioned correction calculation model, a correction factor is obtained, and the digital neutron measurement signal is corrected using the correction factor to obtain the corrected neutron detection signal.

[0012] Based on the corrected neutron detection signal, reactive measurements are performed;

[0013] A three-dimensional core visualization model is established based on the modified calculation model, and the reactivity measurement results are displayed on the three-dimensional core visualization model in numerical form.

[0014] In some implementations, the method of establishing a three-dimensional physical analysis model using a digital modeling approach based on three-dimensional digital coordinate positioning specifically includes:

[0015] Using three-dimensional coordinate positioning equipment or a digital robotic arm, the actual installation position of the reactor core structure is located in three dimensions to obtain the precise three-dimensional coordinates of the reactor core fuel assemblies and internal components; at the same time, the neutron detector and its positioning components used for measurement are located in three dimensions to obtain their corresponding precise three-dimensional coordinates.

[0016] Based on the aforementioned precise three-dimensional coordinates, a Monte Carlo or deterministic three-dimensional physical analysis model is established for subsequent correction calculations and analyses.

[0017] In some embodiments, the method of using a three-dimensional computational model optimization method based on measured critical rod positions to correct the three-dimensional physical analysis model specifically includes:

[0018] Based on the measured parameters of the critical rod position obtained during the experiment, the three-dimensional physical analysis model was verified and optimized online. The specific process included:

[0019] When the deviation of the calculated effective multiplication coefficient of the critical rod position from 1 is greater than a threshold, the three-dimensional physical analysis model is adjusted and optimized within the uncertainty range of the manufacturing parameters of the core component material composition and geometry. The upper and lower limits of each manufacturing parameter after considering the uncertainty are selected as the input of the three-dimensional physical analysis model. According to the influence law of the core component material composition and geometry on the effective multiplication coefficient in reactor physics, the model is optimized so that the deviation of the calculated effective multiplication coefficient of the critical rod position from 1 is reduced to within the threshold range.

[0020] This application employs a model optimization algorithm that takes uncertainty into account to optimize and adjust the physical calculation model, reduce the uncertainty introduced by the correction factor, and improve the efficiency and accuracy of reactivity measurement.

[0021] In some embodiments, the process of adjusting and optimizing the three-dimensional physical analysis model within the uncertainty range of the manufacturing parameters of the core component material composition and geometric manufacturing parameters includes:

[0022] Within the uncertainty range of each manufacturing parameter, each parameter is adjusted in numerical order to optimize the model. During the adjustment process, optimization algorithms are used to accelerate parameter optimization or to perform calculations and analyses on all model inputs. The model with the smallest deviation from 1 in the calculation of the effective multiplication coefficient at the critical rod position is selected as the subsequent correction calculation model.

[0023] In some embodiments, the step of obtaining a correction factor based on the correction calculation model and using the correction factor to correct the digital neutron measurement signal to obtain a corrected neutron detection signal specifically includes:

[0024] Based on the modified calculation model, the neutron flux value at the neutron detector is calculated, and the correction factor is obtained using the neutron flux value.

[0025] The corrected neutron detection signal is obtained by multiplying the digital neutron measurement signal by the correction factor.

[0026] In some embodiments, the reactivity measurement method further includes:

[0027] Based on the modified calculation model, the three-dimensional neutron flux distribution parameters are simulated and analyzed. Combined with the neutron flux reconstruction algorithm, the three-dimensional neutron flux distribution values ​​are obtained.

[0028] By combining visualization techniques, the physical experiment process can be visualized on the three-dimensional reactor core visualization model.

[0029] This application uses a high-precision visualization model to digitally display the measurement results, and can also visualize the three-dimensional neutron flux distribution in the reactor core, which facilitates intuitive and real-time evaluation of the measurement results, enables timely detection of problems and re-measurement of physical parameters, and improves experimental efficiency and accuracy.

[0030] Secondly, this application proposes a digitally visualized reactivity measurement device, the reactivity measurement device comprising:

[0031] The model building unit establishes a three-dimensional physical analysis model using a digital modeling method based on three-dimensional digital coordinate positioning.

[0032] The model correction unit uses a three-dimensional calculation model optimization method based on the measured critical rod position to correct the three-dimensional physical analysis model, thereby obtaining a corrected calculation model.

[0033] A signal correction unit, which obtains a correction factor based on the correction calculation model, and uses the correction factor to correct the digital neutron measurement signal to obtain a corrected neutron detection signal;

[0034] A reactivity measurement unit performs reactivity measurements based on the modified neutron detection signal;

[0035] And a visualization unit, which establishes a three-dimensional core visualization model based on the modified calculation model, and displays the reactivity measurement results in numerical form on the three-dimensional core visualization model.

[0036] Thirdly, this application proposes a digitally visualized reactivity measurement system, the reactivity measurement system comprising:

[0037] A digital measurement front-end, wherein the digital measurement front-end uses a digital signal measurement method to measure a digital neutron measurement signal;

[0038] In addition, a digital analysis platform, which uses the reactivity measurement device described in claim 7 to achieve high-precision digital modeling, reactivity measurement analysis, and visualization.

[0039] In some embodiments, the digital measurement front end includes:

[0040] Neutron detector, used to acquire raw analog neutron measurement signals;

[0041] A signal conditioning module is installed at the tail end of the neutron detector or next to the core. The signal conditioning module is used to condition and amplify the original analog neutron measurement signal and convert it into a digital neutron measurement signal.

[0042] And a communication module, which is used to transmit the digital neutron measurement signal to the digital analysis platform.

[0043] Fourthly, this application proposes a computer device including a memory and a processor, wherein the memory stores a computer program, and the processor executes the computer program to implement the steps of the above-described method.

[0044] This application proposes a digitally visualized reactivity measurement method, apparatus, system, and equipment. In a physics experiment, it improves the accuracy of weak neutron signals by digitizing the front-end signals, enhances the accuracy of the three-dimensional analysis model based on digital positioning coordinate data, and evaluates and corrects the three-dimensional analysis model in real time by combining measured physical parameters such as critical rod positions. Finally, it performs three-dimensional correction calculations and displays the measurement results through a high-precision visualization model, thereby improving measurement efficiency and accuracy, further enhancing the reactivity measurement capability of reactor critical physics experiments, and providing theoretical support for obtaining detailed, accurate, and comprehensive physics experiment data.

[0045] This application proposes a digitally visualized reactive measurement method, apparatus, system, and equipment. To reduce the impact of factors such as signal statistical fluctuations, high-voltage ripples, and electromagnetic interference, it employs a front-end digital measurement method, improving the accuracy and reliability of neutron measurement signals and providing a more accurate and reliable data foundation for subsequent analysis. Furthermore, addressing the limited accuracy of three-dimensional physical calculation models built based on design or empirical parameters, this application also employs a method based on actual three-dimensional digital positioning coordinate data of the reactor core to construct a three-dimensional physical calculation model, improving the model's accuracy and reliability and providing a more precise and reliable calculation model for subsequent measurement analysis. Finally, the application performs three-dimensional correction calculations and displays of the measurement results based on a high-precision visualization model, improving both measurement efficiency and accuracy.

[0046] The present application proposes a digital visualization method, apparatus, system, and device for reactive measurement, which also employs a model optimization algorithm that considers uncertainty to correct the three-dimensional physical calculation model, reduce the uncertainty introduced by the correction factor, and improve the efficiency and accuracy of reactive measurement. Attached Figure Description

[0047] The accompanying drawings, which are included to provide a further understanding of the embodiments of this application and form part of this application, do not constitute a limitation on the embodiments of this application. In the drawings:

[0048] Figure 1 This is a flowchart of the reactivity measurement method proposed in the embodiments of this application;

[0049] Figure 2This is a block diagram illustrating the principle of the reactivity measurement device proposed in the embodiments of this application;

[0050] Figure 3 This is a block diagram illustrating the principle of the reactivity measurement system proposed in an embodiment of this application. Detailed Implementation

[0051] To make the objectives, technical solutions, and advantages of this application clearer, the following detailed description is provided in conjunction with the embodiments and accompanying drawings. The illustrative embodiments and descriptions of this application are only for explaining this application and are not intended to limit this application.

[0052] Example:

[0053] Existing nuclear reactor reactivity measurement results have low visualization capabilities, making it impossible to intuitively and in real-time evaluate the results. Furthermore, existing nuclear reactor reactivity measurement methods typically use design parameters to construct measurement models; however, deviations between actual reactor installation and layout parameters and design parameters limit the accuracy of the measurement models, affecting measurement precision and reliability. To address this, this embodiment proposes a digitally visualized reactivity measurement method. This method employs front-end digital neutron measurement and a digital modeling method based on three-dimensional digital coordinate positioning, combined with digital technologies for visualization and computational analysis, to achieve accurate and reliable measurement and digital display of critical physics experimental parameters for nuclear reactors.

[0054] like Figure 1 As shown, the reactivity measurement method proposed in this embodiment specifically includes the following steps:

[0055] Step 100: A digital neutron measurement signal is obtained by using a signal measurement method based on front-end digitization.

[0056] Because the power of nuclear-powered zero-power physics experiments is extremely low, typically below 50W, the energy of the raw analog signals detected by neutron detectors is low. If these raw analog signals are transmitted via tens of meters of signal cable to secondary instruments in the main control room for conditioning and analysis, they are easily attenuated or affected by environmental electromagnetic signals. To address this, this embodiment uses a neutron detector to measure neutron signals, obtaining raw analog neutron measurement signals. These signals are then directly digitized at the reactor core or at the detector's tail, conditioning, amplifying, and converting the raw analog neutron measurement signals into digital neutron measurement signals. These digital signals are then transmitted to a back-end digital analysis platform for physical parameter measurement and analysis.

[0057] Step 200: Establish a three-dimensional physical analysis model using a digital modeling method based on three-dimensional digital coordinate positioning.

[0058] Existing three-dimensional physical analysis models are typically constructed based on design parameters or empirical parameters. However, deviations exist between the actual parameters of a nuclear reactor core and the design parameters, limiting the accuracy and reliability of the established three-dimensional physical analysis models. To address this, this embodiment employs a three-dimensional coordinate positioning device, or a digital robotic arm or other positioning and installation equipment, to perform three-dimensional coordinate positioning of the actual installation location of the core structure. This obtains the precise three-dimensional coordinates of the core fuel assemblies and internal components. Simultaneously, the neutron detector used for measurement and its casing, among other positioning components, are three-dimensionally positioned to obtain their accurate three-dimensional coordinates. Based on these precise three-dimensional coordinates, a Monte Carlo or deterministic three-dimensional physical analysis model is established for subsequent measurement process analysis and correction calculations.

[0059] It should be noted that the specific methods for constructing the three-dimensional physical analysis model can include Monte Carlo analysis, deterministic methods, etc., which are conventional techniques in this field and will not be elaborated on further here.

[0060] Step 300: The three-dimensional physical analysis model is corrected by using a three-dimensional calculation model optimization method based on the measured critical rod position, resulting in a corrected calculation model.

[0061] A Monte Carlo or deterministic three-dimensional physical analysis model was established using precise positioning coordinate data. Combined with measured parameters of the critical rod position obtained from the experimental process, the three-dimensional physical analysis model was validated and optimized online. The specific validation and optimization process included:

[0062] Calculation of effective proliferation coefficient k at critical rod sites eff When the deviation from 1 is greater than a threshold (e.g., 0.01), the three-dimensional physical analysis model is adjusted and optimized within the uncertainty deviation range of the core component material composition manufacturing parameters and geometric manufacturing parameters. The upper and lower limits of each manufacturing parameter after considering the uncertainty are selected as the input of the three-dimensional physical analysis model. Based on the core component material composition and geometry of the reactor physics major, the effective multiplication coefficient k is determined. eff The influence of the model was investigated, and the effective multiplication coefficient k at the critical rod position was optimized. eff The deviation from 1 is reduced to within the threshold range (i.e., less than or equal to the threshold).

[0063] Preferably, within the uncertainty range of the material composition and geometric manufacturing parameters of the reactor core components, the process of adjusting and optimizing the three-dimensional physical analysis model specifically involves:

[0064] Within the uncertainty range of each manufacturing parameter, each parameter is adjusted sequentially in numerical order (from smallest to largest or from largest to smallest) to optimize the model. During the adjustment process, optimization algorithms such as gradient descent and Newton's method can be used to accelerate parameter optimization, or calculations and analyses can be performed on all model inputs to select the critical rod position and calculate the effective multiplication coefficient k.eff The model with the smallest deviation from 1 is used as the subsequent correction calculation model.

[0065] Step 400: Calculate the correction factor based on the correction calculation model, and use the correction factor to correct the digital neutron measurement signal.

[0066] Based on the above-mentioned corrected calculation model, the digitized neutron signal is analyzed in real time to obtain the corrected digital neutron signal. The original digitized neutron measurement signal obtained by the detector is I. m (t), whose correction formula is as follows:

[0067] I(t)=I m (t)C(t)

[0068] Where I(t) is the corrected neutron signal, and C(t) is the correction factor, which is based on the corrected calculation model and calculates parameters such as the neutron flux at the detector, and is obtained through existing algorithms.

[0069] Step 500: Based on the corrected neutron detection signal, perform reactive measurements.

[0070] Based on the modified detector neutron signal I(t) obtained above, and combined with the following or other reactive measurement formulas, the final reactive measurement result is obtained.

[0071]

[0072] Where Λ is the neutron generation time; β is the effective fraction of delayed neutrons; β i For the i-th group of delayed neutrons; λ i Let be the decay constant of the i-th group of delayed neutrons, and e be the base of the natural logarithm. These parameters are calculated by physics calculation software or other methods. I(t) is the corrected neutron signal, and C is a further correction factor.

[0073] Step 600: Establish a three-dimensional core visualization model based on the modified calculation model, and use the three-dimensional core visualization model to visualize the reactivity measurement results.

[0074] A three-dimensional core visualization model is established based on the modified calculation model, and the reactivity results are displayed on the three-dimensional core visualization model in numerical form.

[0075] In addition, based on the modified calculation model, the distribution parameters such as three-dimensional neutron flux are simulated and analyzed. Combined with neutron flux reconstruction algorithms such as harmonic expansion and neural network algorithms, the three-dimensional refined neutron flux distribution values ​​are obtained. Combined with visualization display methods such as color change and virtual-real change, the physical experiment process is displayed with high precision on the three-dimensional core visualization model.

[0076] The reactivity measurement method proposed in this embodiment improves the accuracy of weak neutron signals at the front end through front-end signal digitization in a single physics experiment. It also enhances the accuracy of the three-dimensional analysis model based on digital positioning coordinate data. Simultaneously, it evaluates and corrects the three-dimensional analysis model in real time by combining measured physical parameters such as critical rod positions. Finally, it performs three-dimensional correction calculations and displays the measurement results through a high-precision visualization model, thereby improving measurement efficiency and accuracy. This further enhances the reactivity measurement capability of nuclear reactor critical physics experiments and provides theoretical support for obtaining detailed, accurate, and comprehensive physics experiment data.

[0077] To mitigate the impact of signal statistical fluctuations, high-voltage ripple, and electromagnetic interference, this embodiment employs a front-end digitization-based measurement method. This improves the accuracy and reliability of the neutron measurement signal, providing a more accurate and reliable data foundation for subsequent analysis. Furthermore, addressing the limited accuracy of three-dimensional physical calculation models built based on design or empirical parameters, this embodiment utilizes a method based on actual three-dimensional digital positioning coordinates of the reactor core to construct the three-dimensional physical calculation model. This enhances the model's accuracy and reliability, providing a more precise and reliable calculation model for subsequent measurement and analysis. Finally, this embodiment employs an optimization algorithm that considers uncertainty to correct the three-dimensional physical calculation model, reducing the uncertainty introduced by the correction factor and improving the efficiency and accuracy of reactivity measurements.

[0078] Based on the same technical concept described above, this embodiment also proposes a digitally visualized reactive measurement device, such as... Figure 2 As shown, the reactivity measurement device proposed in this embodiment includes:

[0079] The model building unit uses a digital modeling method based on three-dimensional digital coordinate positioning to establish a three-dimensional physical analysis model.

[0080] The model correction unit uses a three-dimensional calculation model optimization method based on the measured critical rod position to correct the three-dimensional physical analysis model, resulting in a corrected calculation model.

[0081] The signal correction unit calculates a correction factor based on a correction calculation model and uses this correction factor to correct the digital neutron measurement signal. The digital neutron measurement signal is obtained and uploaded by the digital measurement front end.

[0082] A reactivity measurement unit performs reactivity measurements based on a modified neutron measurement signal.

[0083] In addition, there is a visualization unit, which establishes a three-dimensional core visualization model based on the modified calculation model, and displays the reactivity measurement results through the unit core visualization model.

[0084] It should be noted that the specific implementation process of each functional unit of the above-mentioned reactivity measuring device is as described in the above method, and will not be repeated here.

[0085] This embodiment also proposes a digitally visualized reactive measurement system, such as... Figure 3 As shown, the reactivity measurement system proposed in this embodiment includes:

[0086] The digital measurement front-end employs a signal measurement method based on front-end digitization to obtain a digital neutron measurement signal. Optionally, the digital measurement front-end also includes a neutron detector, a signal conditioning module, and a communication module. The signal conditioning module is located at the tail end of the detector or next to the reactor core. It conditions and amplifies the raw analog neutron measurement signal obtained by the neutron detector and converts it into a digital neutron measurement signal, which is then transmitted to the back-end digital analysis platform via the communication module.

[0087] In addition, a digital analysis platform, which uses the aforementioned reactivity measurement device, enables high-precision digital modeling, reactivity measurement analysis, and visualization.

[0088] Those skilled in the art will understand that embodiments of this application can be provided as methods, systems, or computer program products. Therefore, this application can take the form of a completely hardware embodiment, a completely software embodiment, or an embodiment combining software and hardware aspects. Furthermore, this application can take the form of a computer program product embodied on one or more computer-usable storage media (including but not limited to disk storage, CD-ROM, optical storage, etc.) containing computer-usable program code.

[0089] This application is described with reference to flowchart illustrations and / or block diagrams of methods, apparatus (systems), and computer program products according to embodiments of this application. It will be understood that each block of the flowchart illustrations and / or block diagrams, and combinations of blocks in the flowchart illustrations and / or block diagrams, can be implemented by computer program instructions. These computer program instructions can be provided to a processor of a general-purpose computer, special-purpose computer, embedded processor, or other programmable data processing apparatus to produce a machine, such that the instructions, which execute via the processor of the computer or other programmable data processing apparatus, generate instructions for implementing the flowchart... Figure 1 One or more processes and / or boxes Figure 1 A device that provides the functions specified in one or more boxes.

[0090] These computer program instructions may also be stored in a computer-readable storage medium that can direct a computer or other programmable data processing device to function in a particular manner, such that the instructions stored in the computer-readable storage medium produce an article of manufacture including instruction means, which are implemented in a process Figure 1 One or more processes and / or boxes Figure 1 The function specified in one or more boxes.

[0091] These computer program instructions may also be loaded onto a computer or other programmable data processing equipment to cause a series of operational steps to be performed on the computer or other programmable equipment to produce a computer-implemented process, thereby providing instructions that execute on the computer or other programmable equipment for implementing the process. Figure 1 One or more processes and / or boxes Figure 1 The steps of the function specified in one or more boxes.

[0092] The specific embodiments described above further illustrate the purpose, technical solution, and beneficial effects of this application. It should be understood that the above description is only a specific embodiment of this application and is not intended to limit the scope of protection of this application. Any modifications, equivalent substitutions, improvements, etc., made within the spirit and principles of this application should be included within the scope of protection of this application.

Claims

1. A digitally visualized method for measuring reactivity, characterized in that, The reactivity measurement method includes: Digital neutron measurement signals were obtained using a front-end digitization-based signal measurement method. A three-dimensional physical analysis model is established using a digital modeling method based on three-dimensional digital coordinate positioning. The three-dimensional physical analysis model is modified by using a three-dimensional calculation model optimization method based on measured critical rod positions to obtain a modified calculation model; Based on the aforementioned correction calculation model, a correction factor is obtained, and the digital neutron measurement signal is corrected using the correction factor to obtain the corrected neutron detection signal. Based on the corrected neutron detection signal, reactive measurements are performed; A three-dimensional reactor core visualization model is established based on the modified calculation model, and the reactivity measurement results are displayed on the three-dimensional reactor core visualization model in numerical form; the establishment of a three-dimensional physical analysis model using a digital modeling method based on three-dimensional digital coordinate positioning specifically includes: Using three-dimensional coordinate positioning equipment or a digital robotic arm, the actual installation position of the reactor core structure is located in three dimensions to obtain the precise three-dimensional coordinates of the reactor core fuel assemblies and internal components; at the same time, the neutron detector and its positioning components used for measurement are located in three dimensions to obtain their corresponding precise three-dimensional coordinates. Based on the aforementioned precise three-dimensional coordinates, a Monte Carlo or deterministic three-dimensional physical analysis model is established for subsequent correction calculations and analyses. The method for correcting the three-dimensional physical analysis model using a three-dimensional calculation model optimization method based on measured critical rod positions specifically includes: Based on the measured parameters of the critical rod position obtained during the experiment, the three-dimensional physical analysis model was verified and optimized online. The specific process included: When the deviation of the calculated effective multiplication coefficient of the critical rod position from 1 exceeds a threshold, the three-dimensional physical analysis model is adjusted and optimized within the uncertainty range of the manufacturing parameters of the core component material composition and geometry. The upper and lower limits of each manufacturing parameter after considering uncertainty are selected as the inputs to the three-dimensional physical analysis model. Based on the influence of the core component material composition and geometry on the effective multiplication coefficient according to reactor physics, the model is optimized to reduce the deviation of the calculated effective multiplication coefficient of the critical rod position from 1 to within the threshold range. The specific process of adjusting and optimizing the three-dimensional physical analysis model within the uncertainty range of the manufacturing parameters of the core component material composition and geometry includes: Within the uncertain deviation range of each manufacturing parameter, each parameter is adjusted in numerical order to optimize the model. During the adjustment process, optimization algorithms are used to accelerate parameter optimization or to perform calculations and analyses on all model inputs. The model with the smallest deviation from 1 in the calculation of the effective multiplication coefficient at the critical rod position is selected as the subsequent correction calculation model.

2. The digital visualization method for measuring reactivity according to claim 1, characterized in that, The process of obtaining a correction factor based on the aforementioned correction calculation model, and then using the correction factor to correct the digital neutron measurement signal to obtain the corrected neutron detection signal, specifically includes: Based on the modified calculation model, the neutron flux value at the neutron detector is calculated, and the correction factor is obtained using the neutron flux value. The corrected neutron detection signal is obtained by multiplying the digital neutron measurement signal by the correction factor.

3. The digital visualization method for measuring reactivity according to claim 1, characterized in that, The reactivity measurement method further includes: Based on the modified calculation model, the three-dimensional neutron flux distribution parameters are simulated and analyzed. Combined with the neutron flux reconstruction algorithm, the three-dimensional neutron flux distribution values ​​are obtained. By combining visualization techniques, the physical experiment process can be visualized on the three-dimensional reactor core visualization model.

4. A digitally visualized reactive measurement device, characterized in that, The reactivity measuring device includes: The model building unit establishes a three-dimensional physical analysis model using a digital modeling method based on three-dimensional digital coordinate positioning. The model correction unit uses a three-dimensional calculation model optimization method based on the measured critical rod position to correct the three-dimensional physical analysis model, thereby obtaining a corrected calculation model. A signal correction unit, which obtains a correction factor based on the correction calculation model, and uses the correction factor to correct the digital neutron measurement signal to obtain a corrected neutron detection signal; A reactivity measurement unit performs reactivity measurements based on the modified neutron detection signal; And a visualization unit, which establishes a three-dimensional core visualization model based on the modified calculation model and displays the reactivity measurement results in numerical form on the three-dimensional core visualization model; The aforementioned method for establishing a three-dimensional physical analysis model using a digital modeling approach based on three-dimensional digital coordinate positioning specifically includes: Using three-dimensional coordinate positioning equipment or a digital robotic arm, the actual installation position of the reactor core structure is located in three dimensions to obtain the precise three-dimensional coordinates of the reactor core fuel assemblies and internal components; at the same time, the neutron detector and its positioning components used for measurement are located in three dimensions to obtain their corresponding precise three-dimensional coordinates. Based on the aforementioned precise three-dimensional coordinates, a Monte Carlo or deterministic three-dimensional physical analysis model is established for subsequent correction calculations and analyses. The method for correcting the three-dimensional physical analysis model using a three-dimensional calculation model optimization method based on measured critical rod positions specifically includes: Based on the measured parameters of the critical rod position obtained during the experiment, the three-dimensional physical analysis model was verified and optimized online. The specific process included: When the deviation of the calculated effective multiplication coefficient of the critical rod position from 1 exceeds a threshold, the three-dimensional physical analysis model is adjusted and optimized within the uncertainty range of the manufacturing parameters of the core component material composition and geometry. The upper and lower limits of each manufacturing parameter after considering uncertainty are selected as the inputs to the three-dimensional physical analysis model. Based on the influence of the core component material composition and geometry on the effective multiplication coefficient according to reactor physics, the model is optimized to reduce the deviation of the calculated effective multiplication coefficient of the critical rod position from 1 to within the threshold range. The specific process of adjusting and optimizing the three-dimensional physical analysis model within the uncertainty range of the manufacturing parameters of the core component material composition and geometry includes: Within the uncertain deviation range of each manufacturing parameter, each parameter is adjusted in numerical order to optimize the model. During the adjustment process, optimization algorithms are used to accelerate parameter optimization or to perform calculations and analyses on all model inputs. The model with the smallest deviation from 1 in the calculation of the effective multiplication coefficient at the critical rod position is selected as the subsequent correction calculation model.

5. A digitally visualized reactive measurement system, characterized in that, The reactivity measurement system includes: A digital measurement front-end, wherein the digital measurement front-end uses a digital signal measurement method to measure a digital neutron measurement signal; In addition, a digital analysis platform, which uses the reactivity measurement device described in claim 4 to achieve high-precision digital modeling, reactivity measurement analysis, and visualization.

6. The digitally visualized reactive measurement system according to claim 5, characterized in that, The digital measurement front end includes: Neutron detector, used to acquire raw analog neutron measurement signals; A signal conditioning module is installed at the tail end of the neutron detector or next to the core. The signal conditioning module is used to condition and amplify the original analog neutron measurement signal and convert it into a digital neutron measurement signal. And a communication module, which is used to transmit the digital neutron measurement signal to the digital analysis platform.

7. 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 1-3.

Images