CN121558123A - Neutron generator running state monitoring method and system based on digital twinning - Google Patents
Neutron generator running state monitoring method and system based on digital twinningInfo
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- CN121558123A CN121558123A CN202610090177.8A CN202610090177A CN121558123A CN 121558123 A CN121558123 A CN 121558123A CN 202610090177 A CN202610090177 A CN 202610090177A CN 121558123 A CN121558123 A CN 121558123A
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Abstract
本发明属于数据处理技术领域，涉及一种基于数字孪生的中子发生器运行状态监测方法及系统。该方法采集实时运行电参数构建虚拟孪生体；利用包含粒子注入项与热扩散损耗项的物理差分方程，实时反演靶膜内的有效氘氚原子浓度；通过计算中子管实时阻抗与标称设计阻抗的差异确定束斑漂移修正因子，对虚拟孪生体的束斑面积进行动态修正，解决因电极烧蚀导致的预测模型失效问题；最后基于修正后的状态参数，利用多参数乘积模型预测中子产额并进行健康度诊断。本发明实现了中子管内部状态的透明化监测，有效解决了束斑漂移引起的模型失真难题，提高了全生命周期的预测精度。
This invention belongs to the field of data processing technology and relates to a method and system for monitoring the operational status of a neutron generator based on digital twins. The method collects real-time operating electrical parameters to construct a virtual twin; utilizes a physical difference equation including particle injection and thermal diffusion loss terms to invert the effective deuterium-tritium atom concentration within the target membrane in real time; determines the beam spot drift correction factor by calculating the difference between the real-time impedance and the nominal design impedance of the neutron tube, and dynamically corrects the beam spot area of the virtual twin, solving the problem of prediction model failure caused by electrode ablation; finally, based on the corrected state parameters, a multi-parameter product model is used to predict neutron yield and perform health diagnosis. This invention achieves transparent monitoring of the internal state of the neutron tube, effectively solves the problem of model distortion caused by beam spot drift, and improves the prediction accuracy throughout the entire life cycle.
Description
Technical Field
The invention belongs to the technical field of data processing, and particularly relates to a neutron generator running state monitoring method and system based on digital twinning.
Background
The neutron generator is a core radiation source component of petroleum logging instruments such as a neutron life logging instrument, a carbon-oxygen ratio energy spectrum logging instrument and the like, and the working principle is that a high-voltage electric field is utilized to accelerate the bombardment of deuterium ions on a tritium target to generate fusion reaction, so that fast neutrons are released. For the self-targeted pulse neutron generator commonly used in the prior high-performance logging instrument, the target film is not fixed in advance during manufacturing, but the self-targeted is dynamically formed by injecting the mixed deuterium-tritium gas into the metal film layer in real time during the working process. The process involves complex physical dynamic balance of ion implantation, gas adsorption and thermal diffusion losses, so that the physical state inside the neutron tube is always in immediate evolution.
The current monitoring of the running state of the neutron generator mainly depends on externally measurable macroscopic physical quantities, such as target voltage, target flow intensity, tube shell temperature and neutron counting rate, and the monitoring mode based on external parameters has obvious observability blind areas. On one hand, operators cannot directly know the key microscopic state inside the sealed vacuum tube, particularly the effective adsorption concentration of a target film and the actual spot size of an ion beam bombarded on a target, and on the other hand, neutron yield is a comprehensive function of voltage, current, target efficiency and beam focusing quality, and the specific contribution of each factor is difficult to decouple only by external parameters, so that the evolution mechanism inside a device cannot be truly reflected.
Due to the lack of internal state data, when a drop in the yield of the intermediate occurs, it is difficult to accurately distinguish whether it is caused by degradation of the target film or by device damage. Specifically, the yield of deuterium-tritium gas in the target film is reduced due to heat diffusion loss, and the deuterium-tritium gas can be recovered through aging or supplementary gas, and the electric field distribution is changed due to ablation of an ion source electrode and aging of an insulating part, so that the focusing performance of an ion beam is deteriorated, and beam spots are scattered, and the ion beam is irreversibly physically damaged. The existing monitoring means cannot accurately distinguish the two conditions, so that the neutron tube which can be repaired too early is scrapped, resource waste is caused, or the neutron tube which is damaged due to electrode ablation is subjected to invalid aging, and operation aging is delayed.
Furthermore, existing neutron yield prediction models are typically based on the idealized assumption that the ion beam is uniformly and fixedly impinging on the target, considering the beam spot area as a constant. However, as the electrode ablates, the impedance and focusing capabilities of the ion source drift nonlinearly, resulting in a gradually diverging beam spot and an increasing area. The dynamic change of the physical boundary condition makes the traditional prediction model based on fixed parameters unable to sense the change of the beam current state, and the prediction error increases exponentially with the increase of the running time, finally resulting in model failure. In order to solve the problem that the internal state is invisible and the beam spot drift causes the distortion of the prediction model, a monitoring method capable of inverting the internal state in real time and dynamically correcting the model parameters is highly required.
Disclosure of Invention
The invention aims to provide a neutron generator running state monitoring method and system based on digital twinning, which are used for solving the technical problem that the existing monitoring method cannot reflect the actual state inside a self-targeted neutron tube and beam spot drift to cause the failure of a neutron yield prediction model.
In order to solve the problems, the technical scheme of the neutron generator running state monitoring method based on digital twinning provided by the invention is as follows:
a digital twinning-based neutron generator operating state monitoring method, comprising:
Collecting real-time operation electric parameters of a physical neutron tube, constructing a virtual twin body mapped with the physical neutron tube in a digital space, and initializing physical properties of the virtual twin body;
Simulating a dynamic balance process of deuterium-tritium particles in a target film in the virtual twin body according to the real-time operation electric parameters by using a physical difference equation comprising a particle injection term and a thermal diffusion loss term, and calculating the effective concentration of deuterium-tritium atoms in the target film;
Calculating the difference between the real-time impedance and the nominal design impedance of the physical neutron tube, determining a beam spot drift correction factor according to the difference, and dynamically correcting the beam spot area in the virtual twin body by utilizing the beam spot drift correction factor;
Based on the corrected beam spot area, the effective deuterium-tritium atomic concentration and the real-time operation electric parameter, predicting neutron yield by utilizing a multiparameter product model, and evaluating the health state of the neutron generator by comparing the predicted neutron yield with the actual measured neutron yield, thereby realizing intelligent monitoring of the operation state of the neutron generator.
Further, the physical differential equation satisfies the expression:
In the formula, For the effective concentration of deuterium and tritium atoms in the target film at the next moment,For the effective concentration of deuterium and tritium atoms in the target film at the current moment,For the particle injection rate,In order to achieve a thermal diffusion loss rate,To calculate the step size.
The dynamic balance of particle injection and thermal diffusion loss in the self-targeting formation process is accurately simulated through a physical difference equation, so that accurate internal concentration parameters are provided for subsequent yield prediction, and the problem that the target film state is invisible is solved.
Further, the particle injection rate satisfies the expression:
the thermal diffusion loss rate satisfies the expression:
In the formula, For the real-time target flow intensity,In order to inject the efficiency constant into the cell,In order to be effective in terms of the beam spot area,In order to achieve an effective reaction depth,As a function of the base diffusion coefficient,Is a temperature coefficient of the silicon carbide material,Is the shell temperature.
The invention fully considers the influence of effective reaction depth on the particle injection rate and the influence of temperature on the thermal diffusion loss, so that the evolution simulation of the target film concentration accords with the physical facts better, and the monitoring accuracy is improved.
Further, the beam spot drift correction factor satisfies the expression:
In the formula, For the beam spot drift correction factor,In order to be a focus-sensitive factor,For the real-time target voltage,Designing an impedance for the nominal;
The dynamic correction of the beam spot area in the virtual twin body by using the beam spot drift correction factor comprises the following steps:
multiplying the standard beam spot area in design by the beam spot drift correction factor to obtain an updated beam spot area, and replacing the beam spot area in the virtual twin body by using the updated beam spot area.
Further, the multiparameter product model is specifically configured to multiply a system comprehensive conversion coefficient, a real-time target flow intensity, a voltage gain factor and a real-time target film concentration to obtain the predicted neutron yield;
the comprehensive conversion coefficient of the system is a static constant, and represents inherent physical properties of the neutron generator and geometric efficiency of the detection system, the real-time target flow intensity represents the size of deuterium-tritium ion beam bombarded on a target film in unit time, the voltage gain factor is used for correcting the influence of the change of an accelerating electric field on the deuterium-tritium fusion reaction section, and the real-time target film concentration is the effective deuterium-tritium atomic concentration.
Further, the assessing the health status of the neutron generator includes:
Comparing the predicted neutron yield with the actual neutron yield, if the predicted neutron yield and the actual neutron yield are in a descending trend and the deviation of the predicted neutron yield and the actual neutron yield is within a preset tolerance range, judging that the decrease of the neutron yield is caused by the decrease of the concentration of a target film or the slight divergence of beam spots, belonging to normal aging conforming to a physical rule, and judging that the sudden fault is caused if the decrease of the actual neutron yield exceeds a preset threshold value and the predicted neutron yield is stable.
Further, the injection efficiency constant is obtained through SRIM simulation, and the basic diffusion coefficient is determined by the target film material property.
Further, the comprehensive conversion coefficient of the system comprises the geometric structure and the solid angle physical quantity of the neutron tube, and is obtained through standard scale well calibration.
Further, the real-time operation electric parameters comprise a target voltage sequence, a target flow intensity sequence and a tube shell temperature sequence, and the acquisition frequency is 1kHz.
The invention provides a neutron generator running state monitoring system based on digital twinning, which comprises the following technical scheme:
the neutron generator running state monitoring system based on digital twinning comprises a processor and a memory, wherein the memory stores computer program instructions, and when the computer program instructions are executed by the processor, the neutron generator running state monitoring method based on digital twinning in any one of the technical schemes is realized.
The invention has the beneficial effects that the problem that the traditional monitoring means is difficult to directly sense the microscopic state in the self-targeted neutron tube is effectively solved by constructing the digital twin model of virtual-real mapping. Unlike the prior art that black box type inference is carried out only by depending on external voltage and current, the invention uses a physical difference equation comprising a particle injection item and a thermal diffusion loss item to reproduce the dynamic balance process of target film adsorption and desorption in a digital space, so that operation and maintenance personnel can grasp the evolution condition of the effective deuterium-tritium atomic concentration in the target film in real time through a sealed vacuum tube shell, and the transparent monitoring of the internal state of the neutron generator is realized.
In addition, the invention establishes a beam spot area dynamic correction mechanism based on impedance residual error, and solves the problem that the prediction model is seriously distorted in the later stage of equipment operation due to neglecting ion source electrode ablation in the prior art. The invention utilizes the sensitivity characteristic of the electrical impedance to the focusing state to invert the beam spot drift degree in real time and dynamically adjust the model parameters, thereby forming a correction system with self-adaption capability. This mechanism ensures that the neutron yield prediction accuracy remains at an extremely high level even during the neutron tube aging stage, thereby significantly extending the effective life cycle of the prediction model.
In addition, the intelligent diagnosis strategy of virtual-real comparison improves the accuracy of equipment fault diagnosis. By comparing the theoretical predicted yield of the digital twin with the externally measured yield, the system can accurately distinguish between normal aging caused by natural decay of the target film concentration and sudden failure caused by detector damage or high voltage breakdown. The clear definition of soft and hard faults avoids premature scrapping or invalid aging caused by misjudgment, and optimizes the maintenance decision-making efficiency of the logging instrument.
Drawings
FIG. 1 is a flow chart of steps of a method for monitoring the operating state of a digital twinning-based neutron generator according to the present invention;
FIG. 2 is a schematic diagram of a process for inversion of the operating electrical parameters and beam spot states of a neutron tube according to an embodiment of the invention;
FIG. 3 is a logic diagram of neutron yield prediction bias and fault diagnosis according to an embodiment of the present invention.
Detailed Description
The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings in the embodiments of the present invention.
The invention provides a specific embodiment of a neutron generator running state monitoring method based on digital twinning, which comprises the following steps:
As shown in fig. 1, the digital twinning-based neutron generator operation state monitoring method includes steps S1 to S4, respectively:
s1, acquiring real-time operation electric parameters of a physical neutron tube, constructing a virtual twin body mapped with the physical neutron tube in a digital space, and initializing physical properties of the virtual twin body.
In this step, a data communication link between the physical neutron tube and the digital twin is required to be established. Three core operation electric parameters of the neutron tube in real time, namely a target voltage sequence, a target flow intensity sequence and a tube shell temperature sequence, are acquired through a high-frequency data acquisition interface at a sampling frequency of 1kHz, for example. In order to ensure the usability of the data, the original signal is subjected to moving average filtering to remove high-frequency electromagnetic interference noise. Meanwhile, a virtual twin object is instantiated in an operation memory of the processor, and the initialization process is a process of assigning physical constants and initial states to the virtual twin object, and comprises loading static physical constants and setting initial state variables.
The static physical constants include the nominal design impedance of the neutron tube, the standard beam spot area at design time, the fundamental diffusion coefficient determined by the target film material properties, and the injection efficiency constant obtained by SRIM software simulation. For the neutron tube in the running period, the concentration value stored at the end of the last running time is read from the nonvolatile memory as the current initial concentration.
S2, simulating a dynamic balance process of deuterium-tritium particles in the target film in the virtual twin body according to the real-time operation electric parameters by using a physical difference equation comprising a particle injection term and a thermal diffusion loss term, and calculating the effective concentration of deuterium-tritium atoms in the target film.
The formation of self-targeted is a dynamic equilibrium process, in which, on the one hand, ion beam bombardment injects deuterium-tritium particles into the target film, and on the other hand, the temperature of the target film increases to cause particle loss. The continuous process is discretized into tiny time steps, and the concentration change at each moment is calculated iteratively by using a physical difference equation.
Specifically, the physical difference equation satisfies the expression:
In the formula, For the effective concentration of deuterium and tritium atoms in the target film at the next moment,For the effective concentration of deuterium and tritium atoms in the target film at the current moment,For the particle injection rate,In order to achieve a thermal diffusion loss rate,To calculate the step size.
Wherein the particle injection rate satisfies the expression:
The rate of thermal diffusion loss satisfies the expression:
In the formula, For the real-time target flow intensity,In order to inject the efficiency constant into the cell,In order to be effective in terms of the beam spot area,In order to achieve an effective reaction depth,Is the base diffusion coefficient; for temperature coefficient, the higher the temperature, the faster the gas escapes, Is the shell temperature.
In calculating the particle injection rate, the limitation of the effective reaction depth is fully considered, i.e. only particles staying within a specific depth range are counted into the effective deuterium-tritium atomic concentration. In calculating the heat diffusion loss rate, a temperature coefficient is introduced, and the desorption effect caused by the increase of temperature to exacerbate the thermal motion of gas is simulated.
Therefore, the effective concentration of deuterium and tritium in the target film can be calculated in real time through simulation of a particle balance equation, the problem that the internal state cannot be directly measured is solved, and the dynamic change process of the concentration is clearly described.
S3, calculating the difference between the real-time impedance and the nominal design impedance of the solid neutron tube, determining a beam spot drift correction factor according to the difference, and dynamically correcting the beam spot area in the virtual twin body by utilizing the beam spot drift correction factor.
The method aims at solving the technical problem that the prediction model is gradually distorted due to the fact that the drift of the beam spot area along with time is ignored in the prior art, and creatively utilizes microscopic evolution characteristics of the electrical impedance of the neutron tube to invert the focusing state of the internal ion beam in real time.
From the macro circuit point of view, the equivalent impedance of the neutron tube can be expressed as. However, at the microscopic physical level, the impedance value is not a constant linear resistance, but a physical quantity that couples the ion source geometry with the beam optics. In an ideal high focus state, the transport of the ion beam is significantly affected by space charge effects, exhibiting specific nonlinear impedance characteristics. Over time, the ion source electrode undergoes physical ablation, resulting in distortion of the internal electric field distribution, causing beam spot divergence. This change in microscopic physical boundary conditions will directly map to a macroscopic equivalent impedance that deviates from its original design value. Therefore, there is a strong correlation between the degree of drift of the impedance and the degree of divergence of the beam spot.
The invention constructs a correction model based on the mechanism, and the beam spot drift correction factor meets the expression:
Accordingly, the calculated beam spot drift correction factors are used for updating the beam spot area in the virtual twin body in real time, namely:
In the formula, And the beam spot drift correction factor is used for quantifying the change multiplying power of the beam spot at the current moment relative to the initial state.The focusing sensitivity coefficient is a dimensionless empirical constant calibrated through experiments and is used for adjusting the sensitivity of the impedance residual error to the beam spot area correction weight.For the real-time target voltage,The nominal design impedance is the voltage-current ratio of the neutron tube at a standard working point (such as 100kV/80 uA) under a new tubular state, and the voltage-current ratio is used as a reference zero point for judging the impedance drift.For the standard beam spot area at the time of design,The real-time effective beam spot area after correction.
Through the correction step, when the detected impedance drifts, i.e. the absolute value of the difference between the real-time impedance and the nominal design impedance is larger than 0, the beam spot drift correction factorWill be greater than 1.0, thereby driving the model to automatically increase the beam spot area. The adjustment ensures that the calculation of the particle injection density in the subsequent steps can truly reflect the injection efficiency reduction caused by the aging of the device and the divergence of the beam spots, thereby ensuring the prediction accuracy in the whole life cycle.
Fig. 2 shows a dynamic process of inversion of the physical neutron tube operation electric parameters and the beam spot state, and the diagram consists of two sub-diagrams corresponding to each other. The upper plot depicts the target current intensity and target voltage as a function of operating time, with minor fluctuations in the voltage to current ratio, i.e., the equivalent impedance, occurring in the middle of the operating cycle. The lower sub-graph shows the trend of the beam spot drift correction factor calculated based on the step S3, and when the impedance in the upper sub-graph abnormally fluctuates, the correction factor automatically deviates from the reference value by 1.0 and floats upwards. This dynamic response indicates that the algorithm successfully inverts and recognizes the divergent change in the internal ion beam focus state through the microscopic change in macroscopic electrical parameters.
Therefore, the beam spot divergence caused by device aging can be automatically compensated through dynamic correction based on the impedance residual error, so that the model parameters are always attached to the actual physical state of the neutron tube, and the robustness of the model is greatly improved.
S4, based on the corrected beam spot area, the effective deuterium-tritium atomic concentration and the real-time operation electric parameter, predicting neutron yield by utilizing a multiparameter product model, and evaluating the health state of the neutron generator by comparing the predicted neutron yield with the actual measured neutron yield, so that the intelligent monitoring of the operation state of the neutron generator is realized.
The method comprises the steps of utilizing the beam spot area parameters after dynamic correction in the step S3, combining the effective deuterium-tritium atomic concentration in the target film calculated in the step S2 and the operation electric parameters acquired in real time, constructing a multi-parameter product model to predict neutron yield, and realizing intelligent diagnosis of the health state of equipment through comparison with the actual measured neutron yield.
Specifically, the expression of the multiparameter product model is:
In the formula, To predict neutron yield, i.e., theoretical neutron yield calculated based on the current physical state.The system comprehensive conversion coefficient comprises the geometric structure factor of a neutron tube, the solid angle of a detector and the detection efficiency, is usually obtained through standard scale well experiment calibration, is regarded as a static system constant, and represents the inherent physical property of the neutron generator and the geometric efficiency of the detection system.The voltage gain factor is used for correcting the influence of the change of the accelerating electric field on the deuterium-tritium fusion reaction cross section. The voltage gain factor is approximately square with voltage in the normal working voltage interval and can be generally simplified as,For the real-time target voltage,Is the reference voltage at the nominal time.
The calculated predicted neutron yieldMeasured neutron yield obtained by external neutron detectorReal-time comparison and analysis are carried out, and the running state of the neutron generator is estimated according to the deviation trend of the two:
if the predicted neutron yield and the measured neutron yield are both in a decreasing trend, and the values of the predicted neutron yield and the measured neutron yield are highly fitted, i.e., the deviation of the values is within a preset tolerance range, such as And if the detected decrease amplitude of the neutron yield exceeds a preset threshold value, predicting that the neutron yield remains stable, and judging that the fault is sudden.
Fig. 3 is a schematic diagram showing fault diagnosis logic based on digital twin prediction residual error, wherein scattered points represent actual neutron yield obtained by an external detector, and solid lines represent digital twin prediction neutron yield calculated based on step S4 of the present invention. In most of the operation time period, the solid line and the scattered points show a trend of high coincidence and synchronous slow decline, which proves the extremely high accuracy of the multiparameter product model in the aspect of tracking the normal aging of the equipment, while in the simulation fault stage on the right side of the chart, the actual measured neutron yield is obviously declined, but the prediction curve is still stable because the voltage and current parameters are not abnormal, and a obvious deviation area is formed between the two, namely an abnormal residual error alarm area in the chart, so that the sudden hardware faults can be clearly distinguished from the normal performance attenuation, and a visual basis is provided for the intelligent judgment of the health state of the equipment.
To more intuitively illustrate the meaning and calculation logic of the formulas in the above steps, a specific set of calculation examples are provided below.
First, a scene parameter is set. Wherein the nominal design impedanceStandard beam spot areaFocusing sensitivity coefficientTime stepBasic diffusion coefficientInjection constant termTemperature coefficientComprehensive conversion coefficient of systemReference voltage。
The real-time data collected at the current moment is the target voltageIntensity of target flowShell temperatureTarget membrane concentration at the present momentNormalized values.
Executing step S3, firstly calculating real-time impedance: Then calculate the impedance residual: at this time, the impedance becomes small, which means that the electrical characteristics drift, and then the beam spot drift correction factor is calculated: Correcting the area of the beam spot by using the beam spot drift correction factor, i.e. 。
Step S2 is executed to calculate the particle injection rate: here, use is made of the corrected As denominator. If not, useAs a denominator, the calculation result was 0.008. The reduced implantation rate after correction is seen to represent the physical fact that the larger the beam spot is, the lower the implantation density per unit area is. Calculating the heat diffusion loss rate: calculating the concentration at the next moment: 。
step S4 is executed, and a voltage gain factor is calculated: Calculating predicted neutron yield Neutron/s. If the yield is measured at this timeJudging the health of the equipment, if the measured yield is onlyThen a fault is determined to exist.
The invention provides a specific embodiment of a neutron generator running state monitoring system based on digital twinning, which comprises the following steps:
The neutron generator operation state monitoring system based on digital twin comprises a processor and a memory, wherein the memory stores computer program instructions, and when the computer program instructions are executed by the processor, the neutron generator operation state monitoring method based on digital twin in the above embodiments is realized.
The above system further comprises other components well known to those skilled in the art, such as a communication bus and a communication interface, the arrangement and function of which are known in the art and therefore are not described in detail herein.
While various embodiments of the present invention have been shown and described herein, it will be obvious to those skilled in the art that such embodiments are provided by way of example only. Many modifications, changes, and substitutions will now occur to those skilled in the art without departing from the spirit and scope of the invention.
Claims (10)
1. A method for monitoring the operating state of a neutron generator based on digital twinning, comprising the steps of:
Collecting real-time operation electric parameters of a physical neutron tube, constructing a virtual twin body mapped with the physical neutron tube in a digital space, and initializing physical properties of the virtual twin body;
Simulating a dynamic balance process of deuterium-tritium particles in a target film in the virtual twin body according to the real-time operation electric parameters by using a physical difference equation comprising a particle injection term and a thermal diffusion loss term, and calculating the effective concentration of deuterium-tritium atoms in the target film;
Calculating the difference between the real-time impedance and the nominal design impedance of the physical neutron tube, determining a beam spot drift correction factor according to the difference, and dynamically correcting the beam spot area in the virtual twin body by utilizing the beam spot drift correction factor;
Based on the corrected beam spot area, the effective deuterium-tritium atomic concentration and the real-time operation electric parameter, predicting neutron yield by utilizing a multiparameter product model, and evaluating the health state of the neutron generator by comparing the predicted neutron yield with the actual measured neutron yield, thereby realizing intelligent monitoring of the operation state of the neutron generator.
2. The method for monitoring the operation state of a neutron generator based on digital twinning according to claim 1, wherein the physical difference equation satisfies the expression:
In the formula, For the effective concentration of deuterium and tritium atoms in the target film at the next moment,For the effective concentration of deuterium and tritium atoms in the target film at the current moment,For the particle injection rate,In order to achieve a thermal diffusion loss rate,To calculate the step size.
3. A method for monitoring the operating state of a digital twin-based neutron generator according to claim 2, wherein the particle injection rate satisfies the expression:
the thermal diffusion loss rate satisfies the expression:
In the formula, For the real-time target flow intensity,In order to inject the efficiency constant into the cell,In order to be effective in terms of the beam spot area,In order to achieve an effective reaction depth,As a function of the base diffusion coefficient,Is a temperature coefficient of the silicon carbide material,Is the shell temperature.
4. A method of monitoring the operating state of a digital twin based neutron generator according to claim 3, wherein the beam spot drift correction factor satisfies the expression:
In the formula, For the beam spot drift correction factor,In order to be a focus-sensitive factor,For the real-time target voltage,Designing an impedance for the nominal;
The dynamic correction of the beam spot area in the virtual twin body by using the beam spot drift correction factor comprises the following steps:
multiplying the standard beam spot area in design by the beam spot drift correction factor to obtain an updated beam spot area, and replacing the beam spot area in the virtual twin body by using the updated beam spot area.
5. The method for monitoring the running state of the neutron generator based on digital twinning according to claim 1, wherein the multi-parameter product model is specifically configured to multiply a system comprehensive conversion coefficient, a real-time target flow intensity, a voltage gain factor and a real-time target film concentration so as to obtain the predicted neutron yield;
the comprehensive conversion coefficient of the system is a static constant, and represents inherent physical properties of the neutron generator and geometric efficiency of the detection system, the real-time target flow intensity represents the size of deuterium-tritium ion beam bombarded on a target film in unit time, the voltage gain factor is used for correcting the influence of the change of an accelerating electric field on the deuterium-tritium fusion reaction section, and the real-time target film concentration is the effective deuterium-tritium atomic concentration.
6. The method for monitoring the operation state of a neutron generator based on digital twinning according to claim 1, wherein said assessing the health of the neutron generator comprises:
Comparing the predicted neutron yield with the actual neutron yield, if the predicted neutron yield and the actual neutron yield are in a descending trend and the deviation of the predicted neutron yield and the actual neutron yield is within a preset tolerance range, judging that the decrease of the neutron yield is caused by the decrease of the concentration of a target film or the slight divergence of beam spots, belonging to normal aging conforming to a physical rule, and judging that the sudden fault is caused if the decrease of the actual neutron yield exceeds a preset threshold value and the predicted neutron yield is stable.
7. A method of monitoring the operating state of a digital twinning-based neutron generator according to claim 3, wherein the injection efficiency constant is obtained by SRIM simulation and the base diffusion coefficient is determined by the target film material properties.
8. The method for monitoring the running state of the neutron generator based on digital twinning according to claim 5, wherein the comprehensive conversion coefficient of the system comprises the geometric structure and the solid angle physical quantity of the neutron tube and is obtained through standard scale well calibration.
9. The method for monitoring the operation state of the neutron generator based on digital twinning according to claim 1, wherein the real-time operation electric parameters comprise a target voltage sequence, a target current intensity sequence and a tube shell temperature sequence, and the acquisition frequency is 1kHz.
10. A digital twinning-based neutron generator operating condition monitoring system comprising a processor and a memory, the memory storing computer program instructions which, when executed by the processor, implement a digital twinning-based neutron generator operating condition monitoring method of any one of claims 1-9.
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