Introduction
Neutron flux is an important variable in nuclear reactors. Monitoring the variation and distribution of the neutron flux is essential to maintain the power stability of nuclear reactors [1]. At present, self-powered neutron detectors (SPNDs) are widely employed in core neutron flux measurement systems (CNFMS) of nuclear power plants (NPPs) to accurately measure neutron flux and provide highly reliable three-dimensional (3D) power distribution information. However, the risk of failure has increased with the increasing scale and complexity of the control of modern nuclear reactors [2].
Faulty SPNDs that either completely or partially fail provide incorrect monitoring information, which may negatively affect both the simple and more advanced functionalities of the system, resulting in degradation of the overall system performance and an increased risk level [3]. Techniques to address these problems can be classified as hardware redundancy methods, model-based methods, and data-driven methods [4, 5]. Generally, hardware redundancy measures in which more than three SPNDs are installed to observe the neutron flux within a range of space are employed for NPPs to improve the reliability of CNFMS. Assuming that any one SPND in a neutron measurement channel fails, the additional SPNDs still function and maintain high-accuracy measurements. Although this measure can prevent occasional intermittent failures from negatively affecting the system, the inability to implement fault tolerance can lead to false perceptions of the performance of the CNFMS when redundant SPNDs fail simultaneously. Moreover, redundant SPNDs continue to incur high installation and maintenance costs, which adversely affect the economics of NPPs [6].
Popular model-based methods (such as Kalman filtering [7], mixed Kullback–Leibler divergence and exponential weighted moving average [8], high-gain observer [9], the Monte Carlo method [10], and extended state observer [11]) handle fault detection using simple mathematical models that formulate fault signatures. The results of these methods for specific nonlinear systems have been developed under various restrictive assumptions. Recently, data-driven methods [12-14] have been used to perform fault detection for ker equipment in NPPs; the main principle is to establish an object model based on data analyses and realize accurate detection using model outputs with constraints of the evaluation criteria [15]. Peng et al. [3] constructed mathematical models for various detectors using principal component analysis (PCA) and achieved fault detection and isolation for SPNDs through the square prediction error of linear models and the detector validity index based on the reconstruction. Yellapu et al. [16] developed a method based on multiscale PCA with wavelet transform to reduce the modeling cost and improve the sensor fault diagnosis results by calculating the wavelet approximation coefficient. An online multiscale data reconciliation scheme for detecting and isolating sensor faults in advanced heavy-water reactors was proposed in [17]; the scheme achieved high accuracy under different scenarios. Li et al. [18] employed two different fault identification methods to locate faults more accurately. One was an improved weighted contribution analysis method based on the traditional contribution analysis of sensors to
As a new enabling technology, digital twin (DT) can act as a mirror of the real world by providing an integrated environment for simulating, decision-making, and optimizing physical system operations [22, 23]. Because of the powerful computing capabilities and cognitive intelligence of DT, developing more refined and scalable models for fault detection has become possible. Lin et al. [24] developed a nearly autonomous management and control (NAMAC) system for advanced nuclear reactors with DT technology. Cai et al. [25] proposed analytical techniques based on data and information fusion for modeling and developing DT virtual machine tools. DT applications in the context of NPPs have proliferated recently [26-28]. The development of DT combined with advanced technologies for detection, control, and optimization can significantly improve system performance, reliability, availability, maintainability, and operational flexibility. Therefore, efficient in-core SPND fault detection and the maintenance of monitoring systems using twin technologies are our major objectives. To continue such interesting exploration of research on SPND signals, a twin model using DT technology was constructed for the parameter analysis of an in-core nuclear reactor with large monitoring data and complex and changeable operating conditions. In this case, the established twin model can extract rich values from isolated time-varying data without disturbing the equipment on the real physical layer and can simulate the real-time state and dynamic characteristics of SPND entities through interactive data, overcoming the problem that traditional mathematical models [29] cannot effectively deduce the fault state of multidimensional signals in real time. In addition, several researchers have devoted their attention to state analysis and to the design of DT models of key nuclear reactor components. Hu et al. [30] comprehensively described the research status and development directions of DT technology in the field of advanced nuclear energy, proposed a multidimensional evaluation digital model suitable for application in nuclear reactors, and preliminarily established the fault diagnosis process. Wang et al. [31] proposed a DT system of the out-of-core detector assisted with an installation robot to perform real-time visualization monitoring of the detector installation and replacement process. Gong et al. [32] combined reduced-order models with machine learning to create physics-based DTs using parameters input in real time to rapidly reconstruct the neutron field in the core. Cancemi et al. [33] generated primary nuclear components through numerical simulation of different plant conditions, which may support the predictive maintenance optimization based on plant condition and the development of a DT model for improving plant safety and availability.
Because the implementation of the twin model significantly depends on the information transferred from valid data [34], the frequent and unexpected fault behaviors of SPNDs only provide unrepresentative data, leading to serious distortions in the outcomes and even the unprecedented collapse of the twin model. The decision made after calculations based on a large amount of incorrect information fails to realize the entire purpose of maintaining normal system function. Most recent research methods have focused on fault detection, and only a limited amount of research has been conducted to simultaneously achieve fault tolerance in critical detectors at NPPs. This is one of the principal motivations for this work. Designing a reasonable fault tolerance strategy that would work uninterruptedly with sufficient information-processing capabilities is practically challenging. Li et al. [35] suggested an active fault tolerance control method based on the improved BP neural network, which controls fault sensors by reconstruction. Kim et al. [36] developed a method of evaluating the fault detection coverage of a fault-tolerant technique using a fault injection experiment in a safety-critical digital I&C system for NPPs. They also proposed a probabilistic safety assessment model to observe the effect of the fault detection coverage of fault-tolerant techniques. To enhance the stability of a modular high-temperature gas-cooled reactor system and the control rod drive mechanism, Hui et al. [37] proposed an adaptive fault-tolerant control scheme based on a radial basis function neural network, which has a higher load tracking accuracy and better fault tolerance to systems. Li et al. [38] proposed an active fault-tolerant control scheme based on the deep Q-network algorithm of reinforcement learning to maintain the stability of the once-through steam generator control system. Rangegowda et al. [39] introduced a fault tolerance control framework to arrest the performance degradation of conventional controllers in the presence of sensor bias. Clearly, appropriate fault tolerance operations are required to handle the incorrect information provided by failed equipment, which can ensure data purity and no interference for the normal performance of the twin model. Therefore, introducing an appropriate fault-tolerance strategy to SPND fault detection is advantageous to maintain a healthy interaction of data information and pave the way for reliable outputs of the twin model in the long term.
In this study, we propose an effective fault detection and tolerance approach for in-core SPNDs based on a twin model. The SPNDs are uniformly distributed in the reactor core; a generalized regression neural network (GRNN) [40] is employed to construct the twin model, which is consistent with the real system and represents the common relationship between the overall signals. In this manner, the state correlation between the SPND signals is completely considered, and the output characteristics of specific SPND individuals can be described using the joint feature information of the surrounding SPNDs. Then, state analysis and fault detection of the SPNDs were realized by analyzing the probability distribution of errors between the outputs of the twin model and the real value. To achieve fault tolerance for unexpected faulty SPNDs, we used a weighted k-nearest neighbor (WKNN) [41] to recover and reconstruct faulty signals. Through troubleshooting, data substitution, and data verification of faulty SPNDs, the accuracy and rationality of the detection results can be significantly improved. Compared with the traditional single-signal analysis model, the proposed approach can detect multi-point faults more simply and efficiently.
The remainder of this paper is organized as follows: Section 2 provides a brief description of the measurement channel distribution of the neutron flux and the composition of the SPND. Section 3 describes the construction scheme of the twin model and the specific framework for fault detection and tolerance. The experimental results and discussion are presented in Sect. 4. Finally, the conclusions of the proposed framework are provided in Sect. 5.
Brief Description of SPND
An in-core neutron instrument is one of the most important types of nuclear power equipment. SPNDs provide a crucial basis for neutron flux measurement for safe operation, treatment of abnormal working conditions, and post-accident monitoring of NPPs. In this study, an integrated core instrument casing assembly was used in a pressurized water reactor for third-generation NPPs. As shown in Fig. 1, the core contains 44 radially distributed measurement channels. In each channel, a core detector assembly that is installed in the instrument tube of the fuel assembly contains seven axially distributed SPNDs in equidistant layers.
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SPNDs have been developed to meet the requirements of small size, long life, and high tolerance to harsh environments. The composition of SPNDs is shown in Fig. 2, which mainly consists of an emitter, an insulator, and a collector. The communication line is constructed using a two-core cable in the form of armor and measures the currents generated by the emitter and noise currents caused by the background core. The currents are then transmitted to the processing cabinets through the connector and transmission cable. Because the noise currents are very small, they can be ignored. Generally, rhodium SPNDs are used in pressurized water reactor NPPs. The main generation process of SPND currents is determined by the radiation capture reaction, which proceeds in the emitter material
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Methodology
The purpose of this study is to use the twin model to enhance SPND detection performance. The main goal of the DT model is to create a mirror image of the physical entities in the digital realm by observing the data features and intrinsic correlation information among real SPND signals. In this study, we conducted a further state analysis of the current signals generated by radially distributed SPNDs on the plane of the reactor core of a specific NPP. As shown in Fig. 3,
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Generalized regression neural network
To deal with sample data comprising complicated multi-dimensional variables, prior research concentrated on PCA, clustering, and Kalman filter methods to perform signal analysis of the SPND unit. These techniques can be used to rapidly establish models for axial SPNDs in the same detector assembly. In this study, we aimed to analyze the spatial correlation between the radially distributed SPND variables simultaneously in the plane of the reactor core. The aforementioned technique is not appropriate for large-scale and nonlinear data feature mining; however, the latest neural network algorithms that an distribute information among neurons have significant robustness and can quickly analyze complex nonlinear relationships. As a typical radial basis neural network model based on nonlinear regression theory, GRNN can process high-dimensional data and mine the mutual effects among multiple SPND current features because of its capabilities of nonlinear mapping and high learning speed. Unlike other types of artificial neural networks, GRNN have straightforward structures and training processes. Therefore, we used GRNN as the constituent architecture of the SPND twin model. As shown in Fig. 4, the GRNN is composed of the input, pattern, summation, and output layers. The input and output vectors of the corresponding network are
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There are two types of neuronal calculation formulas in the summation layer. One is to sum the outputs of all the neurons in the pattern layer. The connection weight between each neuron and the pattern layer is set to one. The transfer function can be expressed as
The output layer is calculated by dividing the values obtained using the two formulas in the summation layer baserd on the following equation:
GRNN can be applied to construct different SPND regression submodels that are integrated to form a twin model that outputs twin data.
Construction of the twin model
The state analysis of SPND signals with the application of DT can provide a more efficient and intelligent service for monitoring the neutron flux distribution and its rate. The premise of constructing a twin model is to extract sufficient and effective feature information from physical entities. The reactor core contains
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Fault detection and tolerance
Measuring the residual between the outputs of the twin model and the actual values allows us to ascertain whether faults exist in the detector assemblies. Statistical tests can generally be used to determine the deviation points in a residual sequence. Traditional statistical techniques are sensitive to the presence of outliers because inaccurate data points can distort the mean and standard deviation of a data sequence. In this section, ESD was employed to detect possible outliers in the residual sequence and discriminate the fault from the original signals. ESD can maintain a good elimination effect when several anomalies exist concurrently in the data. We assumed that outliers exist in the residual sequence. The maximum number of outliers was predetermined as
As mentioned above, the simultaneous failures of excessive SPNDs in detector assemblies can lead to anomalously measured data, which cannot accurately represent the actual operational status of the system. A judgment based on fault signals will cause the system to fail to reach its normal operating condition and even cause personnel to misoperate. The capacity of the twin model to perform an effective analysis suffers because of the disordered input, and the reliability and validity of the detection results cannot be demonstrated by the residual information calculated from a broken model. For the CNFMS to be dependable and secure, the fault detection function must be rehabilitated. In this case, we introduce an efficient fault-tolerant strategy, which is implemented before multi-fault detection. The most important factor to consider when designing a fault tolerance solution is that the information that should be available to the entire system after an unexpected failure must be identical to the information that would have been obtained if the SPNDs were not faulty. The main objective was to achieve data recovery, including troubleshooting, data substitution, and data verification.
In the presence of multiple unknown fault sources, fault troubleshooting must be performed using multidimensional data. A possible selection approach involves selecting the vector with the largest calculated residual and performing data recovery first. When executing data substitution, the values of the faulty variables should be replaced with normal signals. To improve the accuracy of the replaced data, the KNN classifier was first used to select
After data substitution, the Jensen–Shannon (JS) divergence [43] was employed to confirm the modified data and guarantee the consistency of the replacement. It can describe the differences between the probability distributions of variables, which perform well in the similarity measurement. For the two probability distributions, the interval value of the JS divergence is
Results and Discussion
In this section, the proposed method was evaluated using historical monitoring data collected from in-core detector assemblies in a third-generation pressurized water reactor. To build a reliable SPND twin model, a sufficient number of measurement datasets must be known in advance. The variables of the 44-dimensional SPND signals, which were distributed radially in a certain layer, were considered as experimental objects in this study. To improve the generalization of the twin model, training data for the twin model were derived from the reactor shutdown stage. As shown in Fig. 6, with the insertion of control rods, the power of the reactor core gradually decreased from 100% FP to 0% FP, and all the currents of SPNDs decreased. The data for the test set were derived from SPNDs during steady operation.
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Performance of the twin model
With the continuous reduction in neutron flux during shutdown, the number of neutrons captured by the emitter decreased, resulting in a proportional decrease in the currents generated by the 44 SPNDs. To extract valuable information from physical SPNDs under different power levels and build a twin model based on it, submodels for 44 dimensional signal variables were executed. First, the training set was segmented round after round, and 44 groups of data patterns with several feature variables
Submodel | RMSE (μA) | Submodel | RMSE (μA) | Submodel | RMSE (μA) | Submodel | RMSE (μA) | ||||
---|---|---|---|---|---|---|---|---|---|---|---|
M1 | 0.3 | 0.0100 | M12 | 0.13 | 0.0024 | M23 | 0.32 | 0.0110 | M34 | 0.05 | 0.0023 |
M2 | 0.09 | 0.0020 | M13 | 0.07 | 0.0022 | M24 | 0.49 | 0.0244 | M35 | 0.02 | 0.0023 |
M3 | 0.23 | 0.0069 | M14 | 0.14 | 0.0029 | M25 | 0.14 | 0.0029 | M36 | 0.17 | 0.0043 |
M4 | 0.22 | 0.0065 | M15 | 0.33 | 0.0115 | M26 | 0.44 | 0.0193 | M37 | 0.07 | 0.0022 |
M5 | 0.34 | 0.0121 | M16 | 0.02 | 0.0023 | M27 | 0.36 | 0.0133 | M38 | 0.13 | 0.0024 |
M6 | 0.16 | 0.0038 | M17 | 0.42 | 0.0176 | M28 | 0.35 | 0.0127 | M39 | 0.05 | 0.0023 |
M7 | 0.06 | 0.0023 | M18 | 0.48 | 0.0233 | M29 | 0.48 | 0.0233 | M40 | 0.03 | 0.0100 |
M8 | 0.12 | 0.0021 | M19 | 0.05 | 0.0023 | M30 | 0.25 | 0.0078 | M41 | 0.32 | 0.0110 |
M9 | 0.02 | 0.0023 | M20 | 0.21 | 0.0061 | M31 | 0.2 | 0.0057 | M42 | 0.22 | 0.0065 |
M10 | 0.44 | 0.0193 | M21 | 0.38 | 0.0146 | M32 | 0.22 | 0.0065 | M43 | 0.11 | 0.0019 |
M11 | 0.45 | 0.0202 | M22 | 0.06 | 0.0023 | M33 | 0.31 | 0.0105 | M44 | 0.14 | 0.0029 |
To demonstrate the superiority of GRNN in modeling more clearly, we compared the proposed method with several typical approaches, including convolutional neural networks (CNN), multilayer perceptron (MLP), extreme gradient boosting (XGB), decision tree (DT), SVM, and Bayesian ridge (BR). All methods were implemented using the same data samples from the test set to compare the output accuracies. As shown in Fig. 7, the twin model formed by GRNN had the lowest RMSE between the model outputs and actual signal values. DT and XGBoost-based models, as common tree regression algorithms, had slightly larger errors than the GRNN-based model, which can easily overfit SPND signals and reduce precision. The learning abilities of the CNN and MLP models for SPND signal features were poorer than that of the GRNN model. These models are suitable for dominant feature extraction but tend to ignore the correlation between the part and whole. SVR- and BR-based models are appropriate for handling small samples instead of analyzing larger multi-dimensional signals. Compared to typical machine learning algorithms, the twin model established based on GRNN can extract rich feature information from isolated time-varying data with lower errors and higher prediction ability. In the subsequent fault detection phase, the errors between the model outputs and actual signals can be used to determine the fault location. The estimated values of the twin model can help improve the in-core power measurement by avoiding interference from fault information.
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Fault detection results under different conditions
The novel contribution of this study is the accurate identification of faulty SPNDs in numerous assemblies using a twin model. The signal characteristics analyzed by the twin model can help examine the fault characteristics. In this section, single- and multi-point SPND fault signals were simulated through experiments to determine the effectiveness of fault detection under different conditions. The faulty SPND signals of diverse measurement channels were simulated by adding different percentages of bias to the normal signals based on the original operating conditions.
For single-point fault detection, as shown in Fig. 8, the deviation between the output of the twin model and the actual normal value is very small before introducing faults into the test set, and the data fit well. In the simulation, a bias of 50% of the normal signal value was introduced into SPND#12 at a time point after the normal signal. In this case, the twin model could maintain a normal output, but the failure of SPND#12 caused the calculated RMSE to fluctuate significantly at this point. The results of the ESD test show that the RMSE of the 12th point deviates the most, which confirms the existence of a faulty SPND#12.
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In reality, complex and changeable interference factors usually cause fault signals to vary. Different types of common fault behaviors mainly include bias, precision degradation, and complete failure, the states of which are abnormal owing to the influence of external environmental factors. The deviation in the signals also varies at the same power level that is used to measure the extent of the magnitude of failures. Experiments (15 groups × 130 rounds) were conducted to compare the fault-detection efficiency under different fault types and deviation rates. The mean accuracy, an evaluation index, is the proportion of the number of successful detections in each group of experiments to the total number of experiments. Table 2 provides the calculation results for fault detection accuracy. Except for the detection accuracy of 99.23% in "5% drifting", the mean accuracies of other cases were 100%, indating that the fault variables identified by the ESD test from errors are consistent with the actual faulty SPNDs. Therefore, the proposed method can maintain an extremely high correct detection rate for single-point SPND faults under various conditions.
Fault types | Mean accuracy with different deviation rates | ||||
---|---|---|---|---|---|
5% | 20% | 40% | 60% | 80% | |
Bias | 100 | 100 | 100 | 100 | 100 |
Drifting | 99.23 | 100 | 100 | 100 | 100 |
Precision degradation | 100 | 100 | 100 | 100 | 100 |
Similarly, it is possible for multiple SPNDs to fail simultaneously. The method for detecting multi-point faults is the same as that for detecting single-point faults. However, this is still a challenge because multiple faulty signals can contaminate the input of the twin model, leading to rising nondeterminacy of the outputs. In this study, we analyzed the impact of the number of faulty SPNDs on the output of a twin model and the fault detection accuracy. Because the type and deviation rate of the failure size had little influence on the detection accuracy, the added simulated fault signals were random in the multi-point fault experiment (44 groups × 150 rounds). The experimental results and comparisons are shown in Fig. 9.
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It was observed that the accuracy of multi-point fault detection remained at 100% when the number of faulty SPNDs was less than 26. In other words, the proposed method can perform a relatively efficient detection when approximately half of the 44 SPNDs fail. As the number of failures continues to increase, the accuracy begins to gradually decrease and approaches 50%, which means that approximately half of the faulty SPNDs detected by ESD are true. Unacceptable data deviating from the normal range is the reason for the occurrence of a sharp fall. Excessive abnormal inputs strongly affect the original function of the twin model and cause it to collapse, hindering the realization of subsequent detection. With ESD test calculation, the multi-point fault detection accuracy of the models based on other algorithms declined earlier than that of GRNN-based models under identical conditions. Their accuracies decreased and slowed to different degrees with the further expansion of failure. Finally, they became more reposeful along their tails. The method proposed in this study performs well for both single- and multi-point SPND fault detection.
Evaluation of fault tolerance
The previous analysis proved the superiority of using the twin model to detect multiple faults. However, there is still a deficiency in dealing with excessive failures, that is, the detection accuracy decreases significantly when the number of faulty signals exceeds the upper limit. Therefore,efficient fault-tolerant solution is required to restore abnormal data. For multi-dimensional fault data points, the KNN algorithm can help search for
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To verify the feasibility of the fault tolerance scheme mentioned above, we selected 100 points of a continuous time sequence under the full-power platform from the test set, and random faults were introduced into SPNDs from the 25th point to the 100th point in the example. In fault-tolerant processing, data recovery is first performed for the SPND variable whose RMSE is the largest. Taking SPND#27 as an example, Fig. 11 shows that the deviation between the fault and original values is distinct (
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For data verification, the JS divergence was employed to prove the similarity of the probability distribution of the values. After the calculation, the divergence values of the fault values, predicted values of the twin model, and regression values of WKNN with the original values were 4.3409×10-5, 7.5058×10-7, and 5.6829×10-7, respectively. The regression values of WKNN have advantages in terms of similarity measurement which verifies the remarkably similar probability distribution and high recovery performance.
We further evaluated the performance of the fault-tolerant method on a sample filled with faulty signals. The impact of the number of recovered variables on the average RMSE of the model outputs and fault detection accuracy is illustrated in Fig. 12. In multi-point fault detection, the obtained detection accuracy with no measures for recovering data was 52.18%, which is the same as before. This is mainly attributed to the fact that the output error of the twin model is much larger than the normal range, which provides completely false knowledge and leads to the inability of the ESD test to determine that all SPND variables have failed. As the data recovery progresses, the faulty variables are substituted by the recovered data. Subsequently, the average RMSE decreases, and the detection accuracy increases gradually. When the number of recovered variables reaches approximately 18, the accuracy increases to approximately 100%. In addition, there is no additional need to recover from other failures in this case.
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Finally, the effects of the fault tolerance strategy on the improvement of twin-model-based fault detection for SPNDs are discussed. As shown in Table 3, the number of faulty SPNDs was divided into five intervals in the multi-point fault detection experiment (150 groups): less than 25, 25–30, 30–35, 35–40, and more than 40. Without the introduction of fault tolerance, the mean fault detection accuracies in the five intervals were 100%, 72.23%, 53.29%, 52.91% and 53.88%. After recovering the faulty data, the number of successfully detected faulty SPNDs increased, resulting in accuracies of 100%. This change confirms that the provision of subsequent fault-tolerant measures to the twin model can efficiently enhance the detection accuracy and improve the capacity to parse the signal correlation for the model, which is sufficient for maintaining healthy monitoring of the system.
Number of failure | Mean accuracy (%) | |
---|---|---|
Before fault tolerance | After fault tolerance | |
≤ 25 | 100 | 100 |
25~30 | 72.23 | 100 |
30~35 | 53.29 | 100 |
35~40 | 52.91 | 100 |
>40 | 53.88 | 100 |
Conclusion
In this study, we proposed a twin-model-based fault-detection method along with a tolerance strategy for in-core SPNDs. The twin model consists of a combination of submodels built by GRNN, which can extract the inner correlation of multi-dimensional data through deep learning from historical SPND signals. Compared with other methods, the twin model can obtain a higher prediction precision and help improve CNFMS measurements. The fault detection phase is based on calculating the error probability distribution of the model outputs that can determine the existence of single-and multi-point faults. This technique can maintain a detection accuracy of nearly 100%. To address the problem of decreased efficiency caused by excessive failures, a fault-tolerant phase was developed with WKNN, which could search for normal signal values with the same operating conditions to replace faulty signals. Comprehensive steps, including troubleshooting, data substitution, and data verification, were conducted to achieve superior the fault-tolerance performance. The experimental results show that the tolerance strategy is promising for delivering high detection quality with an accuracy of more than 99%, suggesting that the proposed method can be considered adoptable. Furthermore, our work can be extended to other layers of in-core detector assemblies to achieve holistic condition-based maintenance of the monitoring system.
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