Digital visual reactivity measurement method, device, system and equipment

Abstract

The invention discloses a digital visual reactivity measurement method, device, system and equipment. The method comprises the following steps: measuring by adopting a signal measurement method based on front-end digitization to obtain a digitized neutron measurement signal; establishing a three-dimensional physical analysis model by adopting a digital modeling method based on three-dimensional digital coordinate positioning; correcting the three-dimensional physical analysis model by adopting a three-dimensional calculation model optimization method based on an actually measured critical rod position to obtain a corrected calculation model; obtaining a correction factor based on the correction calculation model, and correcting the digital neutron measurement signal to obtain a corrected neutron detection signal; carrying out reactivity measurement based on the corrected neutron detection signal; and establishing a three-dimensional reactor core visual model based on the correction calculation model, and displaying the reactivity measurement result on the three-dimensional reactor core visual model in a numerical form. Accurate and reliable digital visual reactivity measurement is realized, and a theoretical basis is provided for efficient and accurate measurement of reactor core reactivity physical parameters.

Description

Technical Field

[0001] The present application relates to the technical field of nuclear reactor reactivity measurement, and in particular to a digital visualized reactivity measurement method, device, system and equipment. Background Art

[0002] In the current nuclear reactor research process, it is necessary to carry out critical physics tests to measure key physical parameters such as reactivity. In the current critical physics test process, a single measurement method is used to measure a single parameter each time, which is time-consuming and inefficient. The measurement results of existing physical tests are generally abstract numbers with low or low visualization levels, and it is impossible to intuitively evaluate the measurement results in real time. If the measurement results are not ideal, it may lead to redoing the test, restarting and stopping the reactor, or even re-disassembling the test core, which will greatly increase the workload and limit the test efficiency and accuracy.

[0003] A lot of research has been done on the measurement methods of reactive physical parameters at home and abroad, and advanced three-dimensional measurement methods such as the inverse dynamic reactivity measurement method based on three-dimensional space-time dynamics have been proposed, and good measurement results have been achieved. However, due to the objective existence of measurement model deviations, the measurement uncertainty of neutron signals and core geometry is difficult to completely eliminate, there are differences between the actual core parameters and the calculation model, and the accuracy of the three-dimensional correction calculation model is limited, and the accuracy of measurement and three-dimensional correction is still limited.

[0004] At present, there are no reports on accurate digital visualization reactivity measurement technology in China. Therefore, it is urgent to study an autonomous and accurate digital visualization reactivity measurement method based on the differences between domestic cores and foreign cores, so as to provide technical support for the efficient and accurate measurement of core reactivity physical parameters. Summary of the invention

[0005] In order to solve the problems of low visualization level in nuclear reactor reactivity measurement methods and limited precision and accuracy of reactivity due to deviations in measurement models, the present application proposes a digital visualization reactivity measurement method, device, system and equipment. The present application adopts a signal measurement method based on front-end digitization to realize the measurement of digital neutron measurement signals, improves the accuracy and reliability of neutron measurement signals, and provides a more accurate and reliable data basis for subsequent analysis; and adopts a modeling method based on the actual three-dimensional digital positioning coordinates of the core to realize the construction of the physical calculation model, avoiding the problem of low accuracy of the physical calculation model caused by the difference between the actual parameters of the core and the design parameters, improving the reliability of the model, and providing a more accurate and reliable calculation model for subsequent measurement and analysis; and uses a high-precision visualization model to digitally display the three-dimensional correction calculation of the reactivity measurement results, which is convenient for intuitive real-time evaluation of the reactivity measurement results and ensures the test efficiency and accuracy.

[0006] This application is implemented through the following technical solutions:

[0007] A digital visualized reactivity measurement method, the reactivity measurement method comprising:

[0008] A digital neutron measurement signal is obtained by measuring the signal using a front-end digitalized 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 corrected by using a three-dimensional calculation model optimization method based on measured critical rod positions to obtain a corrected calculation model;

[0011] Obtaining a correction factor based on the correction calculation model, and using the correction factor to correct the digitized neutron measurement signal to obtain a corrected neutron detection signal;

[0012] Performing reactivity measurement based on the corrected neutron detection signal;

[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 a numerical form.

[0014] In some embodiments, the three-dimensional physical analysis model is established by using a digital modeling method based on three-dimensional digital coordinate positioning, specifically including:

[0015] Use three-dimensional coordinate positioning equipment or digital robotic arms to perform three-dimensional coordinate positioning of the actual installation position of the core structure to obtain the precise three-dimensional coordinates of the core fuel assembly and the internal components of the core; at the same time, perform three-dimensional coordinate positioning of the neutron detector and its positioning components used in the measurement to obtain their corresponding precise three-dimensional coordinates;

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

[0017] In some embodiments, the three-dimensional physical analysis model is modified by using a three-dimensional computational model optimization method based on measured critical rod positions, specifically comprising:

[0018] Combined with the measured parameters of the critical rod position obtained during the test process, the three-dimensional physical analysis model is verified and optimized online. The specific process includes:

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

[0020] This application adopts a model optimization algorithm that takes uncertainty into consideration 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 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, and the specific process 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, an optimization algorithm is used to accelerate parameter optimization or all model input conditions are calculated and analyzed, and the model with the smallest deviation between the critical rod position calculation effective proliferation coefficient and 1 is selected as the subsequent corrected calculation model.

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

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

[0025] The digitized neutron measurement signal is multiplied by the correction factor to obtain a corrected neutron detection signal.

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

[0027] Based on the modified calculation model, a simulation calculation analysis is performed on the three-dimensional neutron flux distribution parameters, and a three-dimensional neutron flux distribution value is obtained in combination with a neutron flux reconstruction algorithm;

[0028] Combined with visualization means, the visualization of the physical test process is achieved on the three-dimensional 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 core, which is convenient for intuitive and real-time evaluation of measurement results, can promptly identify problems and re-measure physical parameters, and improve test efficiency and accuracy.

[0030] In a second aspect, the present application proposes a digital visualized reactivity measurement device, the reactivity measurement device comprising:

[0031] A model building unit, wherein the model building unit uses a digital modeling method based on three-dimensional digital coordinate positioning to establish a three-dimensional physical analysis model;

[0032] A model correction unit, wherein the model correction unit corrects the three-dimensional physical analysis model using a three-dimensional calculation model optimization method based on measured critical rod positions to obtain a corrected calculation model;

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

[0034] a reactivity measurement unit, wherein the reactivity measurement unit performs reactivity measurement based on the corrected neutron detection signal;

[0035] And, a visualization unit, wherein the visualization unit 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] In a third aspect, the present application proposes a digital 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 and obtain a digital neutron measurement signal;

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

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

[0040] A neutron detector, wherein the neutron detector is used to obtain an original simulated neutron measurement signal;

[0041] A signal conditioning module is arranged at the tail end of the neutron detector or beside the core, and 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, wherein the communication module is used to transmit the digitized neutron measurement signal to the digital analysis platform.

[0043] In a fourth aspect, the present application proposes a computer device, comprising a memory and a processor, wherein the memory stores a computer program, and the processor implements the steps of the above method when executing the computer program.

[0044] The present application proposes a digital visualization reactivity measurement method, device, system and equipment. In a physical test, the front-end signal is digitized to improve the accuracy of the front-end weak neutron signal, and the accuracy of the three-dimensional analysis model is improved based on the digital positioning coordinate data. At the same time, the three-dimensional analysis model is evaluated and corrected in real time in combination with the measured critical rod position and other physical parameters. Finally, the three-dimensional correction calculation and display of the measurement results are performed through a high-precision visualization model, which improves the measurement efficiency and accuracy, further improves the reactivity measurement capability level of the reactor critical physical test, and provides theoretical support for obtaining precise, accurate and comprehensive physical test data.

[0045] The present application proposes a digital visualization reactivity measurement method, device, system and equipment. In order to reduce the influence of factors such as signal statistical fluctuations, high-voltage ripples and electromagnetic interference, a measurement method based on front-end digitization is adopted, which improves the accuracy and reliability of neutron measurement signals and provides a more accurate and reliable data basis for subsequent analysis. At the same time, in order to address the problem of limited accuracy of three-dimensional physical calculation models constructed based on design parameters or empirical parameters, the present application also adopts a method based on the actual three-dimensional digital positioning coordinate data of the core to realize the construction of a three-dimensional physical calculation model, which improves the accuracy and reliability of the model and provides a more accurate and reliable calculation model for subsequent measurement and analysis. Finally, the three-dimensional correction calculation and display of the measurement results are performed based on a high-precision visualization model, which improves the measurement efficiency and accuracy.

[0046] The digital visualization reactivity measurement method, device, system and equipment proposed in this application also adopt a model optimization algorithm that takes uncertainty into account to correct the three-dimensional physical calculation model, reduce the uncertainty introduced by the correction factor, and improve the efficiency and accuracy of reactivity measurement. BRIEF DESCRIPTION OF THE DRAWINGS

[0047] The drawings described herein are used to provide a further understanding of the embodiments of the present application, constitute a part of the present application, and do not constitute a limitation on the embodiments of the present application. In the drawings:

[0048] Figure 1 A flow chart of the reactivity measurement method proposed in the embodiment of the present application;

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

[0050] Figure 3 This is a principle block diagram of the reactivity measurement system proposed in an embodiment of the present application. DETAILED DESCRIPTION

[0051] In order to make the objectives, technical solutions and advantages of the present application more clearly understood, the present application is further described in detail below in conjunction with examples and drawings. The illustrative implementation scheme of the present application and its description are only used to explain the present application and are not intended to limit the present application.

[0052] Example:

[0053] The visualization degree of existing nuclear reactor reactivity measurement results is low, and it is impossible to intuitively evaluate the measurement results in real time; in addition, the existing nuclear reactor reactivity measurement method usually uses design parameters to build a measurement model, but there is a deviation between the actual installation and layout parameters of the nuclear reactor and the design parameters, which limits the accuracy of the measurement model and affects the measurement accuracy and reliability. In view of this, this embodiment proposes a digital visualization reactivity measurement method. The reactivity measurement method proposed in this embodiment adopts a front-end digital neutron measurement method and a digital modeling method based on three-dimensional digital coordinate positioning, and combines digital technical means of visualization and computational analysis to achieve accurate and reliable measurement and digital display of nuclear reactor critical physical test parameters.

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

[0055] Step 100: A signal measurement method based on front-end digitization is used to obtain a digital neutron measurement signal.

[0056] Since the power of nuclear power zero-power physical test is extremely low, generally within about 50W, the energy of the original analog signal detected by the neutron detector is relatively low. If the original analog signal is transmitted to the secondary instrument in the main control room through a signal cable of several tens of meters for conditioning and analysis, it is very easy to attenuate or be affected by the environmental electromagnetic signal. In view of this, this embodiment uses a neutron detector to measure the neutron signal, obtains the original analog neutron measurement signal, directly performs front-end digitization beside the core or at the tail of the detector, conditions and amplifies the original analog neutron measurement signal and converts it into a digital neutron measurement signal, and then transmits it to the back-end digital analysis platform for measurement and analysis of physical parameters.

[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 usually constructed based on design parameters or empirical parameters, and there are deviations between the actual parameters of the nuclear reactor core and the design parameters, resulting in the accuracy and reliability of the established three-dimensional physical analysis model being limited. In view of this, this embodiment uses a three-dimensional coordinate positioning device, or a positioning and installation device such as a digital manipulator, to perform three-dimensional coordinate positioning of the actual installation position of the core structure, and obtain the precise three-dimensional coordinates of the core fuel assembly and the internal components of the core. At the same time, the positioning components such as the neutron detector and its casing used in the measurement are three-dimensionally positioned to obtain their accurate three-dimensional coordinates. Based on the above-mentioned precise three-dimensional coordinates, a Monte Carlo or deterministic three-dimensional physical analysis model used for subsequent measurement process analysis is established for subsequent correction calculation analysis.

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

[0060] Step 300, using a three-dimensional computational model optimization method based on measured critical rod positions to correct the three-dimensional physical analysis model to obtain a corrected computational model.

[0061] The Monte Carlo or deterministic three-dimensional physical analysis model established by precise positioning coordinate data is combined with the test process to obtain the measured parameters of the critical rod position, and the three-dimensional physical analysis model is verified and optimized online. The specific verification and optimization process includes:

[0062] Calculation of effective multiplication coefficient k at critical rod position eff When the deviation from 1 is greater than a threshold value (for example, 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, and the upper and lower limit values ​​of each manufacturing parameter after considering the uncertainty are selected as the input of the three-dimensional physical analysis model. The effective multiplication coefficient k is calculated based on the core component material composition and geometry of the reactor physics major. eff The influence law of the model is optimized so that the critical rod position calculates the effective proliferation coefficient k eff The deviation from 1 decreases to within the threshold range (ie, less than or equal to the threshold).

[0063] Preferably, within the uncertainty deviation range of the core component material composition manufacturing parameters and geometric manufacturing parameters, the three-dimensional physical analysis model is adjusted and optimized as follows:

[0064] Within the uncertainty range of each manufacturing parameter, adjust each parameter in numerical order (from small to large or from large to small) to optimize the model. During the adjustment process, the gradient descent method, Newton method and other optimization algorithms can be used to accelerate parameter optimization, or all model input conditions can be calculated and analyzed, and the critical rod position can be selected to calculate the effective proliferation coefficient k.eff The model with the smallest deviation from 1 is used as the subsequent correction calculation model.

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

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

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

[0068] Among them, I(t) is the corrected neutron signal, and C(t) is the correction factor, which is based on the correction calculation model, calculates the neutron flux value and other parameters at the detector, and is obtained through the existing algorithm.

[0069] Step 500, performing reactivity measurement based on the corrected neutron detection signal.

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

[0071]

[0072] Where Λ is the neutron generation time; β is the effective fraction of delayed neutrons; β i is the delayed neutron fraction of the i-th group; i is the decay constant of the i-th group of delayed neutrons, e is the base of the natural logarithm, and the above parameters are calculated by physical calculation software or other calculation 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 perform core visualization display of the reactivity measurement results through the three-dimensional core visualization model.

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

[0075] In addition, based on the modified calculation model, simulation calculation and analysis are carried out on the distribution parameters such as the three-dimensional neutron flux. Combined with the 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 changes and virtual and real changes, high-precision visualization of the physical test process is achieved on the three-dimensional core visualization model.

[0076] The reactivity measurement method proposed in this embodiment improves the accuracy of the front-end weak neutron signal by digitizing the front-end signal in a physical test, improves the accuracy of the three-dimensional analysis model based on the digital positioning coordinate data, and evaluates and corrects the three-dimensional analysis model in real time in combination with the measured critical rod position and other physical parameters. Finally, the three-dimensional correction calculation and display of the measurement results are performed through a high-precision visualization model, thereby improving the measurement efficiency and accuracy, further improving the reactivity measurement capability of the nuclear reactor critical physical test, and providing theoretical support for obtaining precise, accurate and comprehensive physical test data.

[0077] In order to reduce the influence of factors such as signal statistical fluctuations, high-voltage ripples, and electromagnetic interference, this embodiment adopts a measurement method based on front-end digitization, which improves the accuracy and reliability of neutron measurement signals and provides a more accurate and reliable data basis for subsequent analysis; at the same time, in order to address the problem of limited accuracy of three-dimensional physical calculation models built based on design parameters or empirical parameters, this embodiment also adopts a method based on the actual three-dimensional digital positioning coordinates of the core to realize the construction of a three-dimensional physical calculation model, which improves the accuracy and reliability of the model and provides a more accurate and reliable calculation model for subsequent measurement and analysis. This embodiment also adopts an optimization algorithm that takes uncertainty into consideration to correct the three-dimensional physical calculation model, reduce the uncertainty introduced by the correction factor, and improve the efficiency and accuracy of reactivity measurement.

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

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

[0080] A model correction unit uses a three-dimensional computational model optimization method based on measured critical rod positions to correct the three-dimensional physical analysis model to obtain a corrected computational model.

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

[0082] The reactivity measurement unit performs reactivity measurement based on the corrected neutron measurement signal.

[0083] And, a visualization unit, which establishes a three-dimensional core visualization model based on the modified calculation model, and performs core visualization display of 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 measurement device is as described in the above-mentioned method, and will not be repeated here.

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

[0086] A digital measurement front end, which uses a signal measurement method based on front-end digitization to measure and 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 arranged at the tail end of the detector or next to the core, and conditions and amplifies the original analog neutron measurement signal obtained by the neutron detector and converts it into a digital neutron measurement signal, and transmits the digital neutron measurement signal to the back-end digital analysis platform through the communication module.

[0087] And, a digital analysis platform, which adopts the above-mentioned reactivity measurement device to achieve high-precision digital modeling, reactivity measurement analysis and visual display.

[0088] Those skilled in the art will appreciate that the embodiments of the present application may be provided as methods, systems, or computer program products. Therefore, the present application may adopt the form of a complete hardware embodiment, a complete software embodiment, or an embodiment in combination with software and hardware. Moreover, the present application may adopt the form of a computer program product implemented in one or more computer-usable storage media (including but not limited to disk storage, CD-ROM, optical storage, etc.) that include computer-usable program code.

[0089] The present application is described with reference to the flowcharts and / or block diagrams of the methods, devices (systems), and computer program products according to the embodiments of the present application. It should be understood that each process and / or box in the flowchart and / or block diagram, as well as the combination of the processes and / or boxes in the flowchart and / or block diagram, can be implemented by computer program instructions. These computer program instructions can be provided to a processor of a general-purpose computer, a special-purpose computer, an embedded processor, or other programmable data processing device to generate a machine, so that the instructions executed by the processor of the computer or other programmable data processing device generate instructions for implementing the processes in the flowchart and / or block diagram. Figure 1 A process or multiple processes and / or boxes Figure 1 A device that provides the functions specified in a block or multiple blocks.

[0090] These computer program instructions may also be stored in a computer-readable memory capable of directing a computer or other programmable data processing device to operate in a specific manner, so that the instructions stored in the computer-readable memory produce an article of manufacture comprising an instruction device, which implements the process Figure 1 A process or multiple processes and / or boxes Figure 1 A function specified in one or more boxes.

[0091] These computer program instructions can also be loaded onto a computer or other programmable data processing device so that a series of operating steps are executed on the computer or other programmable device to produce a computer-implemented process, thereby providing instructions for implementing the process. Figure 1 A process or multiple processes and / or boxes Figure 1 The steps for the functions specified in one or more boxes.

[0092] The specific implementation methods described above further illustrate the purpose, technical solutions and beneficial effects of the present application in detail. It should be understood that the above description is only the specific implementation method of the present application and is not intended to limit the scope of protection of the present application. Any modifications, equivalent substitutions, improvements, etc. made within the spirit and principles of the present application should be included in the scope of protection of the present application.

Claims

1. A digital visualization reactivity measurement method, characterized in that: The reactivity measurement method comprises: A digital neutron measurement signal is obtained by measuring the signal using a front-end digitalized 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 corrected by using a three-dimensional calculation model optimization method based on measured critical rod positions to obtain a corrected calculation model; Obtaining a correction factor based on the correction calculation model, and using the correction factor to correct the digitized neutron measurement signal to obtain a corrected neutron detection signal; Performing reactivity measurement based on the corrected neutron detection signal; 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 a numerical form.

2. A digital visualized reactivity measurement method according to claim 1, characterized in that: The digital modeling method based on three-dimensional digital coordinate positioning is used to establish a three-dimensional physical analysis model, which specifically includes: Use three-dimensional coordinate positioning equipment or digital robotic arms to perform three-dimensional coordinate positioning of the actual installation position of the core structure to obtain the precise three-dimensional coordinates of the core fuel assembly and the internal components of the core; at the same time, perform three-dimensional coordinate positioning of the neutron detector and its positioning components used in the measurement to obtain their corresponding precise three-dimensional coordinates; Based on the above precise three-dimensional coordinates, a Monte Carlo or deterministic three-dimensional physical analysis model is established for subsequent correction calculation and analysis.

3. A digital visualized reactivity measurement method according to claim 1, characterized in that: The three-dimensional physical analysis model is modified by using the three-dimensional computational model optimization method based on the measured critical rod position, specifically including: Combined with the measured parameters of the critical rod position obtained during the test process, the three-dimensional physical analysis model is verified and optimized online. The specific process includes: When the deviation of the effective multiplication coefficient calculated at the critical rod position from 1 is greater than a threshold value, the three-dimensional physical analysis model is adjusted and optimized within the uncertainty deviation range of the core component material composition manufacturing parameters and the geometric manufacturing parameters, and the upper and lower limit values ​​of each manufacturing parameter after considering the uncertainty are selected as the input of the three-dimensional physical analysis model. According to the influence of the core component material composition and geometry of the reactor physics major on the effective multiplication coefficient, the model is optimized so that the deviation of the effective multiplication coefficient calculated at the critical rod position from 1 is reduced to within the threshold range.

4. A digital visualized reactivity measurement method according to claim 3, characterized in that: 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 specific process includes: Within the uncertainty range of each manufacturing parameter, each parameter is adjusted in numerical order to optimize the model. During the adjustment process, an optimization algorithm is used to accelerate parameter optimization or all model input conditions are calculated and analyzed, and the model with the smallest deviation between the critical rod position calculation effective proliferation coefficient and 1 is selected as the subsequent corrected calculation model.

5. A digital visualized reactivity measurement method according to any one of claims 1 to 4, characterized in that: The method of obtaining a correction factor based on the correction calculation model and using the correction factor to correct the digitized neutron measurement signal to obtain a corrected neutron detection signal specifically includes: Based on the correction calculation model, the neutron flux value at the neutron detector is calculated, and the correction factor is calculated using the neutron flux value; The digitized neutron measurement signal is multiplied by the correction factor to obtain a corrected neutron detection signal.

6. A digital visualized reactivity measurement method according to any one of claims 1 to 4, characterized in that: The reactivity measurement method further comprises: Based on the modified calculation model, a simulation calculation analysis is performed on the three-dimensional neutron flux distribution parameters, and a three-dimensional neutron flux distribution value is obtained in combination with a neutron flux reconstruction algorithm; Combined with visualization means, the visualization of the physical test process is achieved on the three-dimensional core visualization model.

7. A digital visual reactivity measurement device, characterized in that: The reactivity measurement device comprises: A model building unit, wherein the model building unit uses a digital modeling method based on three-dimensional digital coordinate positioning to establish a three-dimensional physical analysis model; A model correction unit, wherein the model correction unit corrects the three-dimensional physical analysis model using a three-dimensional calculation model optimization method based on measured critical rod positions to obtain a corrected calculation model; A signal correction unit, wherein the signal correction unit obtains a correction factor based on the correction calculation model, and uses the correction factor to correct the digitized neutron measurement signal to obtain a corrected neutron detection signal; a reactivity measurement unit, wherein the reactivity measurement unit performs reactivity measurement based on the corrected neutron detection signal; And, a visualization unit, wherein the visualization unit 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.

8. A digital visual reactivity measurement system, characterized in that: The reactivity measurement system comprises: A digital measurement front end, wherein the digital measurement front end uses a digital-based signal measurement method to measure and obtain a digital neutron measurement signal; And, a digital analysis platform, which uses the reactivity measurement device described in claim 7 to achieve high-precision digital modeling, reactivity measurement analysis and visual display.

9. A digital visualized reactivity measurement system according to claim 8, characterized in that: The digital measurement front end comprises: A neutron detector, wherein the neutron detector is used to obtain an original simulated neutron measurement signal; A signal conditioning module is arranged at the tail end of the neutron detector or beside the core, and 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, wherein the communication module is used to transmit the digitized neutron measurement signal to the digital analysis platform.

10. 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, the steps of the method according to any one of claims 1 to 6 are implemented.

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