Introduction
Escalating global energy consumption exacerbates climate change, underscoring the critical need for carbon emission mitigation strategies to address environmental challenges [1]. As a nearly carbon-free power source, nuclear energy plays a significant role in mitigating the global greenhouse effect and addressing global warming [2, 3]. The widespread implementation of nuclear energy relies predominantly on nuclear power plants (NPPs) that harness nuclear fission reactions. Compared with traditional energy sources, NPPs have more stringent safety requirements owing to their complex nature and the potential hazards associated with radioactive materials [4].
In pursuit of nuclear reactor designs with enhanced safety and economic viability, the Generation IV International Forum (GIF) proposed six reactor technologies for future development, among which molten salt reactors (MSRs) are considered a promising alternative [5-8]. MSRs exhibit exceptional inherent safety characteristics owing to their unique design and operating principles. In these reactors, liquid molten salt serves a dual function as both the nuclear fuel carrier and primary coolant, efficiently transferring heat from the core [9]. The safety advantages of MSRs are reflected in several aspects: (1) operation at near-atmospheric pressure, (2) strong negative reactivity temperature feedback combined with a large void coefficient [10, 11], (3) low proliferation risk, and (4) immunity to fuel irradiation damage or mechanical failure [12-15]. Despite these inherent safety features, potential risks associated with operational anomalies and accidents remain significant concerns. Therefore, accurate and timely accident diagnosis is essential to prevent the escalation of abnormal events and mitigate their consequences, serving as an external safeguard for reactor operation.
Currently, accident diagnosis in NPPs relies primarily on conventional threshold-monitoring approaches and human expertise [16]. Although operators are typically well trained, they may experience significant psychological stress during NPP accidents, making it challenging to accurately assess the nature of an accident within a limited time frame. Consequently, further research on accident diagnosis technologies for nuclear energy systems is urgently needed. Developing systems capable of accurately and efficiently identifying accidents is essential for supporting prompt decision-making during emergency response.
Accident diagnosis strategies for NPPs are generally classified into two methodological approaches: model-driven and data-driven. Model-based methods require the formulation of precise mathematical representations that capture the fundamental physical principles governing system behavior [17]. The continuous evolution of industrial technologies and computational capabilities has propelled modern nuclear systems toward increasingly sophisticated architectures characterized by large-scale designs, complex structures, and distributed configurations [18]. However, the inherent complexity of nuclear phenomena, coupled with uncertainties in input parameters [19], poses significant challenges for developing high-fidelity models capable of accurately representing the behavior of these advanced systems.
Data-driven methodologies, in contrast, establish diagnostic frameworks through statistical analysis of operational data, thereby eliminating the requirement for explicit modeling of complex parameter interactions [20]. Such approaches exploit the inherent correlations among system parameters by developing data-driven models in which complex interdependencies are automatically captured during the training process. This paradigm has led to extensive research and practical applications of machine learning techniques in nuclear system diagnostics, including support vector machines (SVMs) [21], ensemble decision trees (DTs) [22], adaptive nearest-neighbor algorithms (KNN) [23], artificial neural networks (ANNs) [24, 25], and multivariate statistical analysis [26].
However, with the rapid advancement of artificial intelligence (AI), along with the deployment of advanced sensors and high-speed data transmission mechanisms, operational datasets reflecting reactor status have begun to exhibit big data characteristics. These developments have rendered conventional data-driven methods potentially insufficient for the demands of the emerging nuclear big data era. To address these limitations, deep learning architectures have emerged as a viable solution with remarkable capabilities for diagnosing anomalies and accidents in nuclear systems [27-30].
Among deep learning architectures, convolutional neural networks (CNNs) have gained significant attention in fault diagnostic applications owing to their strong capability for extracting high-dimensional and complex features [31]. For example, researchers have developed an enhanced CNN architecture incorporating mini-batch processing optimization, which has been successfully implemented in nuclear system diagnostics, achieving higher accuracy and providing valuable guidance for operators [32]. Additionally, a multiclassification framework based on a CNN architecture was developed to detect core disturbances and abnormal operational signatures, demonstrating high robustness and practical potential [33]. In a recent study, an SSA-CNN-LSTM model for NPP fault diagnosis was proposed, achieving a classification accuracy of 98.24% through CNN-LSTM parameter optimization using the sparrow search algorithm, thereby enhancing nuclear safety and reducing hazards caused by human error [34].
However, a persistent limitation of conventional deep learning architectures is performance degradation as the network depth increases, which can adversely affect classification accuracy [35]. This issue has been addressed by introducing deep residual CNNs (ResNets) [36]. Compared with traditional CNNs, ResNets employ identity shortcut connections that reduce the difficulty of training deep architectures, thereby improving the model’s discriminative capability for complex classification tasks. As a result, ResNets have gradually gained popularity in fault diagnosis applications [37-41].
For example, adaptive wavelet transform features have been integrated with the ResNet architecture to enhance the fault detection capability of planetary gear transmission systems [37]. Sun and Wang developed several diagnostic models by integrating multilayer perceptrons (MLPs), CNNs, recurrent neural networks (RNNs), and ResNets, and compared their performance using a dataset from Case Western Reserve University [38]. Zhao et al. adopted an adaptive parametric rectified linear unit (ReLU) in ResNet to improve feature learning capability, which was validated through fault diagnosis applications [40]. Yao et al. proposed an innovative diagnostic framework incorporating adaptive residual convolutional networks specifically designed for anomaly identification in small modular reactor (SMR) operational systems [41].
These studies provide useful references for applying the residual CNN (RCNN) method to diagnostic tasks in the nuclear energy field. However, several issues still require further consideration and improvement:
Nuclear energy systems consist of numerous subsystems and a large number of monitoring parameters. These datasets often exhibit high-dimensional characteristics, posing significant challenges for data analysis and decision-making. To improve model learning efficiency and performance, feature selection techniques should be implemented to identify the optimal feature subset for classification.
In practical applications, data collected in NPPs are often contaminated by noise. Therefore, it is necessary to combine the RCNN structure with an attention mechanism to enhance the model’s robustness to noise.
In NPPs, different accidents may exhibit similar signals during their early stages. RCNNs typically use ReLUs as activation functions, which have a constant slope and zero output in the negative region. This property may reduce effective feature learning capability, thereby limiting model performance. Therefore, an activation function with more dynamic parameters should be incorporated into the model to enhance classification capability.
Hyperparameter optimization is essential for improving the performance of deep learning models. An in-depth investigation of hyperparameters should therefore be conducted for the proposed network to maximize its effectiveness.
To address the aforementioned challenges and improve accident diagnosis efficiency in nuclear energy systems, this study proposes a three-step methodology. First, Pearson correlation analysis and random forest importance ranking are used for feature selection. Next, a modified RCNN framework, termed an adaptive antinoise module RCNN (AM-RCNN), is developed for MSR accident diagnosis by integrating an antinoise module and adaptive parametric ReLUs. Finally, Bayesian optimization (BO) is applied to adjust the model’s hyperparameters.
The remainder of this paper is organized as follows. Section 2 outlines the methodological framework of the proposed approach. Section 3 presents the case study for the nuclear accident diagnosis model. Section 4 compares the results with those of alternative models and describes the optimization process. Finally, Sect. 5 concludes the paper with key findings and potential directions for future research.
Methodology
Feature selection technique
Feature selection is a methodological approach for extracting the most relevant subset of attributes from a comprehensive feature space based on predefined optimization criteria and statistical evaluation metrics. This process aims to retain only the most relevant features from a dataset, thereby reducing the scale of data processing by eliminating redundant and irrelevant variables.
Pearson correlation coefficient
The Pearson correlation coefficient is a widely used statistical measure for feature selection tasks, quantifying the degree of linear dependence between paired variables. This metric evaluates the strength of the association between two random variables by analyzing their joint variability, which is represented through their covariance structure. Mathematically, the Pearson correlation coefficient for variables α and β can be expressed as Eq. (1) [42], where 
Random forest variable importance
Random forests are a class of nonlinear predictive models that aggregate multiple decision trees for regression or classification tasks. Individual trees within the ensemble are generated using a bootstrap sampling process, in which each tree is constructed from an independently drawn random subset of the training data.
Random forest models provide variable importance measures that help identify features contributing significantly to class separation. Among these measures, permutation importance is one of the most commonly used approaches. This method sequentially shuffles the values of each predictor variable and evaluates the corresponding reduction in the predictive performance of the model. Shuffling a variable disrupts its relationship with the outcome; therefore, a substantial decrease in classification accuracy after permutation indicates a strong predictive relationship between that feature and the target variable.
The permutation-based importance score 
For tree ensembles, the importance scores from individual trees can be averaged to obtain an overall measure of feature importance [43].
Residual convolutional neural networks (RCNNs)
CNNs represent a class of deep-learning architectures that employ multiple filters to hierarchically process input samples through convolution and pooling operations across successive layers [27]. Building on this concept, RCNNs introduce skip connections to effectively address the model degradation problem [35, 36]. Instead of relying solely on deeper network structures to approximate complex hidden nonlinearities, RCNNs facilitate the learning of residual representations, which simplifies the optimization process. The architectural configuration of RCNNs is illustrated in Fig. 1.

The transformation from input to output can be expressed as follows [36]:




Anti-noise module
In this study, an anti-noise (AN) architecture that combines a soft threshold function with an attention mechanism integrated into an RCNN is proposed. The resulting framework, termed AM-RCNN, enhances noise robustness in MSR accident diagnosis.
The soft thresholding (ST) operator is a widely adopted denoising technique in signal processing applications. Its fundamental principle involves threshold contraction: when the input exceeds a predefined threshold value, the output approaches this boundary; otherwise, it is set to zero. This mechanism effectively suppresses noise interference while preserving signal characteristics. The mathematical representation is as follows [44]:

The global average pooling (GAP) operation in this submodule computes channel-wise mean values while preserving essential feature information. Parallel to this path, a compact network processes the GAP outputs through two sequential fully connected layers, culminating in a sigmoid activation function that generates scaling factors within the [0, 1] range. This auxiliary network incorporates batch normalization and PReLU layers for feature normalization and nonlinear activation, respectively. The resulting adaptive threshold τ is obtained by multiplying the GAP-derived averages by the scaling coefficients produced by the compact network.
Bayesian theory-based optimization
Hyperparameters play a crucial role in machine learning algorithms because they directly influence the training process and significantly affect model performance. Tuning these hyperparameters often requires professional knowledge and expert experience. Consequently, hyperparameter tuning represents a challenging optimization problem with an implicit objective function. BO is a powerful approach for addressing such optimization problems [46]. Figure 3 presents the workflow of BO.

The BO process begins by defining the hyperparameter space, which encompasses the feasible value ranges for each tunable parameter. The optimization procedure then begins by sampling an initial set of configurations for model training and validation. Following performance evaluation, an acquisition strategy determines the next parameter combination for evaluation, guided by probabilistic surrogate models.
This process iterates through successive cycles, refining the parameter selection based on the performance observed in previous iterations. The iterative procedure continues until a predefined termination condition is satisfied. Once this condition is met, the optimization process concludes by identifying the hyperparameter configuration that yields the best model performance.
To provide a comprehensive and intuitive visualization of the computational procedure, a flowchart summarizing the integrated methodology is presented in Fig. 4. The flowchart illustrates the step-by-step procedure of the proposed methodology. The process begins with feature selection using Pearson correlation analysis and random forest importance ranking, followed by the construction and training of the AM-RCNN model. BO is then applied to fine-tune the model’s hyperparameters, ultimately yielding an optimized diagnostic model for MSR accident scenarios.

Case study
A designed MSR description
In 2011, the Chinese Academy of Sciences (CAS) initiated a strategic research program focusing on advanced nuclear fission energy systems, in which MSR technology represented a key development pathway. As part of this initiative, the TMSR program [5], a pioneering effort in MSR technology development, was conducted by the Shanghai Institute of Applied Physics (SINAP), CAS. The MSR investigated in this study corresponds to the design version proposed in the TMSR program [47-49]. Figure 5 illustrates the conceptual design of the reactor, and Table 1 summarizes its key technical specifications [50].

| Main parameter | Design value |
|---|---|
| Thermal power | 2 MWth |
| Fuel salt flow rate | 50 kg/s |
| Fuel salt temperature (inlet/outlet) | 630 ℃/650 ℃ |
| Coolant salt flow rate | 42 kg/s |
| Coolant salt temperature (inlet/outlet) | 560 ℃/580 ℃ |
The reactor adopts a dual-loop molten salt configuration. The primary loop, designated as the fuel–salt system, comprises a core vessel, primary heat exchanger, circulation pump, and connecting piping. The fuel salt circulates upward from the bottom plenum through the core and then flows into the shell side of the heat exchanger via the circulation pump. Thermal energy is subsequently transferred to the secondary loop, after which the cooled fuel salt completes the cycle by returning to the bottom plenum.
The secondary loop, referred to as the coolant salt system, contains a circulation pump, air-cooled heat exchanger, and associated piping. The coolant salt flows through the tube side of the primary heat exchanger, absorbs thermal energy from the primary loop, and releases heat to the atmosphere through the air-cooled exchanger. Furthermore, the MSR design incorporates a passive reactor vessel air cooling system (RVACS) for effective decay heat removal.
Operation scenario data collection
Given the limited availability of operational data for MSRs, accident diagnosis datasets were generated using the RELAP5-TMSR simulation code. This specialized tool, developed at SINAP [51, 52], extends RELAP5/MOD4.0 with enhanced capabilities for liquid-fueled reactor analysis. The accuracy of the code has been verified through experiments conducted on a high-temperature molten-salt natural circulation test bench [53, 54], and it is currently applied in the design and analysis of MSR systems. Figure 6 illustrates the nodal configuration, where the primary circuit components are labeled 0XX, while 1XX and 2XX denote the secondary loop and the air-cooling system, respectively. The RVACS is modeled using nodes 301–306.

In this study, eight typical operational scenarios are considered: one steady-state condition and seven transient events. By training the model using data that include both steady-state and transient conditions, the model’s generalization capability is improved, enabling comprehensive accident detection across a wide range of operating states. Table 2 lists these operational conditions.
| Operation scenario | Description |
|---|---|
| I (normal) | Steady state |
| II (accident) | Uncontrolled withdrawal of a control rod (shim rod) |
| III (accident) | Uncontrolled withdrawal of a control rod (regulating rod) |
| IV (accident) | Coolant circulating pump rotor seizure |
| V (accident) | Loss of air flow of the molten salt-air heat exchanger |
| VI (accident) | Fuel circulating pump speed increases unexpectedly |
| VII (accident) | Coolant circulating pump speed increases unexpectedly |
| VIII (accident) | Loss of offsite power |
Given the varying transient characteristics at different power levels, each scenario was generated at reactor power levels ranging from 10% to 120% of full power (FP) in increments of 10% FP. The resulting dataset comprised more than 550,000 data samples, with each sample consisting of 21 monitoring parameters aligned with the architecture of the instrumentation and control system. The data-partitioning scheme allocated 70% of the dataset for model training, while equal proportions of 15% were reserved for validation and testing.
Additionally, to prevent the diagnostic system from ignoring variables with small absolute values caused by differences in measurement scales, the Z-score normalization method was adopted [55].
Feature selection
The 21 monitored parameters are listed in Table 3.
| Monitoring parameter | Unit |
|---|---|
| 0-Reactivity | $ |
| 1-Reactor power | MW |
| 2-Fuel circulating pump speed (FCPS) | rpm |
| 3-Coolant circulating pump speed (CCPS) | rpm |
| 4-Fuel salt mass flow rate (FSMFR) | kg/s |
| 5-Coolant salt mass flow rate (CSMFR) | kg/s |
| 6-Air mass flow rate of the molten salt-air heat exchanger (AMFR) | kg/s |
| 7-Core inlet temperature (CIT) | ℃ |
| 8-Middle core temperature (MCT) | ℃ |
| 9-Core outlet temperature (COT) | ℃ |
| 10-Upper plenum temperature (UPT) | ℃ |
| 11-Tube side inlet temperature of the primary heat exchanger (TITHE) | ℃ |
| 12-Tube side outlet temperature of the primary heat exchanger (TOTHE) | ℃ |
| 13-Tube side inlet temperature of the molten salt-air heat exchanger (TITSHE) | ℃ |
| 14-Tube side outlet temperature of the molten salt-air heat exchanger (TOTSHE) | ℃ |
| 15-Air side inlet temperature of the molten salt-air heat exchanger (AITSHE) | ℃ |
| 16-Air side outlet temperature of the molten salt-air heat exchanger (AOTSHE) | ℃ |
| 17-Power of PRVACS | kW |
| 18-Air mass flow rate of the PRVACS | kg/s |
| 19-Air inlet temperature of PRVACS | ℃ |
| 20-Air outlet temperature of PRVACS | ℃ |
Assuming that all monitoring parameters are used as input features would impose a substantial computational burden, thereby compromising the efficiency and performance of the model. Therefore, feature selection was performed to reduce redundant variables among these parameters.
Reactor monitoring systems typically generate multiple interdependent parameters in which strong correlations may exist (e.g., perfectly correlated variables contain redundant information and can be represented by a single parameter). Therefore, the Pearson correlation metric was used as the primary statistical tool to quantify the linear dependence among system variables. The Pearson correlation coefficients between variables are shown in Fig. 7, where features 0–20 correspond to the parameters listed in Table 3.

A Pearson correlation coefficient with an absolute value exceeding 0.8 is commonly considered to indicate a strong correlation between two parameters [56]. However, this threshold should be evaluated within the specific context of the application. In practical scenarios, when two parameters exhibit strong correlation, preference is typically given to retaining the parameter that is easier to measure and has higher measurement accuracy.
Following this principle, a parameter-screening process was conducted to evaluate parameter significance across three correlation thresholds:
Uncorrelated features in machine learning models may act as noise sources, potentially reducing model accuracy by introducing classification bias. The random forest variable importance method was therefore applied to identify the relevance between variables and classes. The evaluation and ranking of feature importance are shown in Fig. 8. To ensure that the selected features effectively support the model’s diagnostic capability, scenarios with relative importance thresholds of 0.05 and 0.10 were examined during the parameter-screening process. Rigorous testing indicated that the model achieved the best performance with a threshold of 0.05. Consequently, all seven parameters were retained in the final feature set to preserve diagnostic accuracy and ensure robust system performance.

Model structure and hyperparameter setting
The structure of the AM-RCNN model for MSR accident diagnosis, which integrates advanced deep-learning methodologies, is shown in Fig. 9, and Table 4 provides details of the AM-RCNN architecture.

| Layer number | Layer type | ||
|---|---|---|---|
| 1 | Input | ||
| 2 | Convolution | ||
| 3 | Shortcut | BN | |
| 4 | PReLU | ||
| 5 | Convolution | ||
| 6 | BN | ||
| 7 | PReLU | ||
| 8 | Convolution | ||
| 9 | AN module | GAP | |
| 10 | Linear | ||
| 11 | BN | ||
| 12 | PReLU | ||
| 13 | Linear | ||
| 14 | Sigmoid | ||
| 15 | BN | ||
| 16 | PReLU | ||
| 17 | Convolution | ||
| 18 | GAP | ||
| 19 | Flatten | ||
| 20 | Dropout | ||
| 21 | Linear | ||
| 22 | Softmax | ||
The AM-RCNN adopts a four-convolutional-layer architecture with batch normalization layers and activation functions incorporated throughout the network to enhance performance. It integrates several key components, including a residual mapping module for feature transformation, an anti-noise (AN) processing unit for signal enhancement, and a GAP layer for feature aggregation.
The subsequent layers include a tensor-flattening operation for dimensionality reduction, a dropout regularization layer to mitigate overfitting [57], and a fully connected transformation layer for feature classification. The network employs a softmax activation function for final classification decisions, while utilizing parametric ReLUs (PReLUs) throughout the model to improve feature representation learning [58]. The shortcut connection in the residual architecture from Layers 3 to 14 is automatically adapted to either identity mapping or a convolutional layer to maintain dimensional consistency with the main network structure. The AN processing module spanning network layers 9–14 is described in detail in Sect. 2.3 and illustrated in Fig. 2.
Evaluation index
Model performance was evaluated using confusion matrices [59], which provide a detailed analysis of classification performance. As illustrated in Fig. 10, the matrix structure for multiclass problems assigns distinct labels to each category, with diagonal elements indicating correct predictions. The row sums correspond to the number of samples belonging to each actual class.

In addition, the evaluation incorporated accuracy and the F1-score metric. Classification accuracy is a fundamental performance indicator that quantifies the ratio of correctly predicted instances to the total number of samples. The F1-score represents the harmonic mean of precision and recall and is particularly sensitive to the lower value between these two measures. Higher F1-scores indicate improved model performance, especially in handling imbalanced classification tasks. Detailed definitions of precision, recall, F1-score, and diagnostic accuracy are provided in Eqs. (10)–(13) [60].



Results and discussion
Model performance and comparison
The case study primarily evaluated the proposed AM-RCNN against conventional CNN and RCNN architectures, focusing on comparative training and testing performance within similar network frameworks.
Figure 9 illustrates the architectural differences among the baseline CNN, standard RCNN, and the proposed AM-RCNN approach. To ensure consistency, the number of convolutional layers in both the RCNN and CNN models was fixed at four, matching that of the AM-RCNN. In addition, the other layers in the main structures of the RCNN and CNN were identical to those of the AM-RCNN. The shortcut structure in the RCNN was configured as identity mapping.
The training procedure employed cross-entropy as the optimization objective function. Model parameter optimization was performed using stochastic gradient descent (SGD) with momentum acceleration and L2 regularization. The convolutional and fully connected layers were initialized using Kaiming and Xavier initialization methods [61, 62], respectively. Based on prior training experience, the model hyperparameters were configured as follows: a learning rate of 0.005 for gradient updates, a dropout probability of 0.5 for regularization, a mini-batch size of 128 samples per iteration, and 200 training epochs.
To prevent overfitting and determine the optimal model configuration, an early stopping strategy was adopted. The validation loss function served as the primary convergence criterion, triggering early termination when no improvement was observed over ten consecutive training epochs. In such cases, the model parameters corresponding to the minimum validation loss, typically occurring ten epochs prior to termination, were retained as the optimal configuration.
Figure 11 presents the epoch-wise progression of training loss and validation accuracy across the different models, revealing several key observations.

According to the training loss curves, the proposed AM-RCNN model converged faster than the RCNN and CNN models. This indicates that the AM-RCNN model exhibits enhanced generalization capability and operational robustness, making it particularly suitable for deployment in noisy environments and transfer-learning scenarios.
The proposed AM-RCNN model triggered early stopping at the 28th epoch, compared with the 62nd epoch for RCNN and the 90th epoch for CNN. This demonstrates that the AM-RCNN model has stronger learning capability and stability, reducing training time and computational cost and making it suitable for flexible or real-time application environments.
All three models achieved high validation accuracy, exceeding 90%. Specifically, the validation accuracy of the proposed AM-RCNN model exceeded 95%, reaching 97%, while the RCNN achieved 95% and the CNN reached 94%.
Figure 12 and Table 5 present the classification results for all evaluated models on the test dataset, including the confusion matrices and performance metrics (accuracy and F1-score). This analysis yielded several significant findings.

| Operation scenario | CNN | RCNN | AM-RCNN | |
|---|---|---|---|---|
| F1-score (%) | I (normal) | 89.8 | 92.4 | 93.9 |
| II (accident) | 80.4 | 85.5 | 93.7 | |
| III (accident) | 84.7 | 88.1 | 93.3 | |
| IV (accident) | 100 | 100 | 100 | |
| V (accident) | 96.9 | 97.0 | 97.3 | |
| VI (accident) | 99.9 | 100 | 100 | |
| VII (accident) | 100 | 100 | 100 | |
| VIII (accident) | 100 | 100 | 100 | |
| Average F1-score (%) | 93.9 | 95.4 | 97.2 | |
| Accuracy (%) | 94.4 | 95.7 | 97.3 | |
The accuracy of the AM-RCNN model on the test set is consistent with that on the validation set, further demonstrating the model’s generalization capability.
Analysis of the true positive and true negative rates in the confusion matrices indicates accurate identification of all operational scenarios across all models. These findings demonstrate precise identification of critical system parameters associated with different operational scenarios. Comparative analysis revealed mean F1-scores of 93.9% for conventional CNN architectures, 95.4% for standard RCNN implementations, and 97.2% for the proposed AM-RCNN framework.
The relatively lower F1-scores observed for accident II, accident III, and steady-state conditions can be attributed to the inherent difficulty of distinguishing scenarios with overlapping feature distributions during certain operational phases. Specifically, accidents II and III, both reactivity insertion accidents, share the same triggering mechanism and exhibit similar development trends, making accurate classification particularly challenging. Similarly, certain transient accident conditions were misclassified as steady-state conditions because the dynamic evolution of key parameters during the early stages of accidents often resembles steady-state behavior.
The proposed model demonstrates superior performance in differentiating accidents II and III compared with conventional CNN and RCNN architectures, reflecting enhanced feature extraction and pattern-recognition capabilities.
Robustness test
Liquid-fueled MSR operational environments inherently contain multiple noise sources that affect detector readings, necessitating a rigorous evaluation of the robustness of the diagnostic model.
Real-world operational conditions typically exhibit composite noise characteristics arising from multiple sources. For analytical purposes, the mixed noise was approximated as Gaussian white noise. The noise impact was quantified using the signal-to-noise ratio (SNR), which evaluates the relative strength between the target signal and background interference. The SNR is mathematically defined as follows [63]:
Monitoring signals in NPPs generally maintain relatively low noise levels, with vibration measurements typically exceeding 30 dB SNR [64]. This threshold was therefore used as the baseline for assessing model robustness, and the corresponding test results are presented in Fig. 13 and Table 6. The results indicate that all three models performed well in noisy environments, achieving diagnostic accuracy exceeding 90%. In particular, the accuracy and F1-score of the proposed model remained close to 97%.

| Operation scenario | CNN | RCNN | AM-RCNN | |
|---|---|---|---|---|
| F1-score (%) | I (normal) | 85.7 | 86.8 | 93.0 |
| II (accident) | 75.3 | 81.1 | 92.5 | |
| III (accident) | 77.2 | 81.6 | 91.8 | |
| IV (accident) | 100 | 100 | 100 | |
| V (accident) | 93.7 | 95.1 | 97.3 | |
| VI (accident) | 99.9 | 99.9 | 100 | |
| VII (accident) | 100 | 100 | 100 | |
| VIII (accident) | 100 | 100 | 100 | |
| Average F1-score (%) | 91.5 | 93.1 | 96.8 | |
| Accuracy (%) | 92.1 | 93.4 | 96.9 | |
As shown in Fig. 14, the performance of all three models decreased in noisy environments, with the conventional CNN model experiencing the most significant decline. Performance evaluation under noisy conditions revealed reductions of 2.4% in classification accuracy and 2.6% in the F1 metric for the conventional CNN architecture. Similarly, the standard RCNN implementation exhibited an equivalent decrease of 2.4% in both performance metrics. In contrast, the proposed AM-RCNN framework demonstrated superior noise resilience, with only a 0.4% reduction in both metrics. This result highlights the effectiveness of the integrated anti-noise processing module in maintaining model stability.

Model optimization
To further enhance the performance of the AM-RCNN model, hyperparameter optimization was conducted using the BO method. In training deep neural networks, the learning rate, batch size, and dropout rate are critical hyperparameters that significantly influence learning efficiency, convergence speed, and model generalization capability. Consequently, these hyperparameters were selected as the primary optimization variables in this study.
The hyperparameter search space was defined as follows: the learning rate ranged from 1×10-4 to 1×10-1; the batch size was randomly selected from the discrete set {32, 64, 128, 256}; and the dropout rate ranged from 0.1 to 0.6.
Figure 15 presents the results of the BO for diagnostic performance. The optimized configuration achieved 98.3% accuracy, representing a 1% improvement over the baseline model, with the following optimal parameters: a learning rate of 0.0003, a batch size of 256, and a dropout rate of 0.28.

Conclusions
To satisfy the safety and reliability requirements of advanced nuclear energy systems and reduce excessive manual intervention during operation, research on intelligent accident diagnosis systems is crucial for the future development of MSRs. This paper proposes AM-RCNN with an anti-noise module and a parametric activation function, and validates it using a designed MSR. The key contributions and distinctive features of the developed methodology are summarized as follows:
Rather than being limited to individual components or isolated subsystems, the selected input features comprehensively represent the operational state of the entire reactor system architecture. These parameters were systematically filtered for MSR accident diagnosis using Pearson correlation analysis and random forest importance ranking methods, thereby reducing data dimensionality and improving model efficiency.
Compared with traditional RCNN and CNN models, the proposed approach demonstrates improved diagnostic performance, particularly in noisy environments.
A BO framework was implemented for automated hyperparameter tuning, specifically targeting the learning rate, mini-batch size, and regularization parameters. This optimization strategy further improved the diagnostic performance of the AM-RCNN architecture, yielding a classification accuracy of over 98% when using the optimized model configuration.
The developed model provides real-time operational decision support for MSRs and has potential applications in other energy systems. Its architecture also offers a framework for developing deep-learning-based diagnostic approaches.
Future research directions include: (1) advanced data preprocessing techniques, (2) heuristic optimization algorithms for model refinement, and (3) adaptive learning rate strategies to enhance training efficiency. Furthermore, sequential deep learning architectures, including LSTM networks and gated recurrent units, will be explored and integrated into a predictive analytics framework for MSR anomaly detection and early warning systems.
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