Fault Diagnosis for Key Nuclear Power Plant Systems and Equipment Based on Knowledge Graphs and Bayesian Networks
Abstract
1. Introduction
2. Materials and Methods
2.1. Fault Knowledge Modeling
2.1.1. Knowledge Graph Fundamentals
2.1.2. Knowledge Extraction Strategy
2.1.3. KG to Network Structure Conversion
2.2. Fault Inference Model
2.2.1. Bayesian Networks
2.2.2. Bayesian Network Learning
2.2.3. Construction of Bayesian Network Inference Engine
3. Results
3.1. Key Systems and Equipment
3.2. Fault Mechanism Analysis
3.3. Validation and Analysis
3.3.1. NPP System Faults
3.3.2. Ablation Study and Comparative Analysis
3.3.3. NPP Equipment Faults
4. Discussion
4.1. Ablation Study
4.2. Comparative Analysis
4.3. Interpretability and Causal Reasoning
4.4. The Phenomenon of Feature Drift in Fault Evolution
5. Conclusions
Author Contributions
Funding
Data Availability Statement
Conflicts of Interest
References
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| Entity | Relationship | Entity |
|---|---|---|
| Primary loop hot leg break | cause | Steam generator outlet flow rate |
| Primary loop hot leg break | cause | Containment pressure |
| Primary loop hot leg break | cause | Containment sump water level |
| Primary loop hot leg break | cause | Pressurizer water level |
| Primary loop hot leg break | cause | Containment internal temperature |
| Primary loop hot leg break | cause | Containment internal radioactivity |
| Pressurizer water level | lead to | Pressurizer pressure |
| Pressurizer pressure | lead to | Charging flow rate |
| Pressurizer pressure | lead to | Letdown flow rate |
| Pressurizer pressure | lead to | Thermal power of electric heaters |
| Pressurizer pressure | lead to | Pressurizer vapor space temperature |
| Pressurizer pressure | lead to | Pressurizer surge line temperature |
| Thermal power of electric heaters | lead to | Pressurizer vapor space temperature |
| Fault Name | Moderate | Severe | Minor |
|---|---|---|---|
| Primary loop hot leg break | 0.15 | 0.2 | 0.1 |
| Charging line leakage | 0.1 | 0.15 | 0.05 |
| Volume control tank leakage | 0.1 | 0.2 | 0.05 |
| Hot Leg Break | Charging Line Leakage | Volume Control Tank Leakage | |
|---|---|---|---|
| Prior probability | 0.3294 | 0.3367 | 0.3339 |
| Fault Name | Pressurizer Level | −1 | 0 |
|---|---|---|---|
| Pressurizer pressure | −1 | 0.5223 | 0.2488 |
| 0 | 0.1562 | 0.5024 | |
| 1 | 0.3215 | 0.2488 | |
| Pressurizerpressure | −1 | 0 | |
| Electric heater power | 0 | 0.4287 | 0.6734 |
| 1 | 0.5713 | 0.3266 |
| Model | Configurations |
|---|---|
| SDG | edge_sign_logic = (ratio_same/diff > 0.33), propagate_mode = ‘BFS_with_conflict_resolution’, decision_threshold = 0.5, parallel_diagnoser = True |
| SVM | kernel = [‘rbf’, ‘linear’], C = [0.1, 1, 10, 100], gamma = [1, 0.1, 0.01, 0.001, ‘scale’], probability = True |
| DG-softmax | backbone = 1D-CNN (Conv-BN-MaxPool x2, Conv-BN-GAP x1), epochs = 40 (pre-train) + 20 (DG-train), batch_size = 20, optimizer = Adam(lr = 0.001), loss = CategoricalCrossentropy(from_logits = True), margin_logic = Adaptive PCA-distribution distance |
| LSTM | self.lstm = nn.LSTM(input_size = 1, hidden_size = 128, batch_first = True) self.dropout = nn.Dropout(p = 0.2) self.fc1 = nn.Linear(128, 48); self.relu = nn.ReLU() self.fc2 = nn.Linear(48, num_classes); Optimizer = Adam(lr = 0.01) Loss = CategoricalCrossentropy; Epochs = 200 |
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© 2026 by the authors. Licensee MDPI, Basel, Switzerland. This article is an open access article distributed under the terms and conditions of the Creative Commons Attribution (CC BY) license.
Share and Cite
Cui, Y.; Sun, Y.; Wang, H.; Chen, S.; Ren, H.; Peng, M.; Lu, R. Fault Diagnosis for Key Nuclear Power Plant Systems and Equipment Based on Knowledge Graphs and Bayesian Networks. Processes 2026, 14, 1903. https://doi.org/10.3390/pr14121903
Cui Y, Sun Y, Wang H, Chen S, Ren H, Peng M, Lu R. Fault Diagnosis for Key Nuclear Power Plant Systems and Equipment Based on Knowledge Graphs and Bayesian Networks. Processes. 2026; 14(12):1903. https://doi.org/10.3390/pr14121903
Chicago/Turabian StyleCui, Yan, Yu Sun, Hang Wang, Shijun Chen, Hebin Ren, Minjun Peng, and Ruixin Lu. 2026. "Fault Diagnosis for Key Nuclear Power Plant Systems and Equipment Based on Knowledge Graphs and Bayesian Networks" Processes 14, no. 12: 1903. https://doi.org/10.3390/pr14121903
APA StyleCui, Y., Sun, Y., Wang, H., Chen, S., Ren, H., Peng, M., & Lu, R. (2026). Fault Diagnosis for Key Nuclear Power Plant Systems and Equipment Based on Knowledge Graphs and Bayesian Networks. Processes, 14(12), 1903. https://doi.org/10.3390/pr14121903
