融合物理约束与数据驱动的核电厂安全关键参数智能预测方法研究

Research on Physics-informed and Data-driven Intelligent Prediction Method for Safety-critical Parameters of Nuclear Power Plant

  • 摘要: 针对核电厂传统热工水力高精度仿真效率低且代价高以及纯数据驱动模型缺乏物理约束、预测可信性不足等问题,本研究提出一种融合物理约束与数据驱动的关键参数智能预测方法。构建融合无量纲机理参数(如雷诺数Re、普朗特数Pr、努塞尔数Nu)约束特征的代理模型,以弥补纯数据驱动方法的不足;建立基于自注意力机制的Transformer时序代理模型,实现复杂事故演化过程的高精度快速预测;开展不确定性量化与可解释性分析,提升预测结果的可信性。在此基础上,以压水堆小破口失水事故为案例,利用RELAP5程序对燃料包壳峰值温度(PCT)进行预测。结果表明:引入物理机理参数后,代理模型预测精度得到提升(均方误差MSE=21.995,平均绝对百分比误差MAPE=3.171%),不确定度(区间评分IS=9.16)降低27.8%,计算时间由分钟量级降至毫秒量级。该方法实现了事故演化过程中关键参数的高效预测与可解释分析,可为核电厂灵活运行及多事故情景下的安全监测与预警提供技术支撑。

     

    Abstract: To meet the requirements for real-time, accurate, and reliable prediction of safety-critical parameters under nuclear power plant accident conditions, this study proposed a physics-informed and data-driven intelligent prediction method for safety-critical parameters in nuclear power plants. The thermal-hydraulic system codes can describe complex accident progression with strong physical consistency. However, their relatively high computational cost limits their application in rapid prediction and online early-warning scenarios. In contrast, purely data-driven models can improve computational efficiency, but they often suffer from insufficient physical constraints, uncertain prediction reliability, and limited interpretability. To address these issues, this study developed a time-series surrogate modeling framework by combining thermal-hydraulic mechanism knowledge with data-driven learning. First, the RELAP5 code was used to model and simulate a small-break loss-of-coolant accident (SBLOCA) in the main coolant pipe of a pressurized water reactor, generating high-fidelity accident data under multiple operating conditions. Then, mutual information analysis and mechanism-based understanding were combined to select key input features from system operating parameters, coolant properties parameters, and dimensionless physical parameters. Dimensionless parameters, including the Reynolds number (Re), Prandtl number (Pr), and Nusselt number (Nu), were introduced to enhance the model representation of flow and heat-transfer processes. Based on these features, a Transformer-based time-series surrogate model was constructed to perform multi-step prediction of peak cladding temperature (PCT). Furthermore, Monte Carlo dropout was used to obtain predictive distributions, and the interval score (IS) was adopted to quantitatively evaluate the quality of prediction intervals and the level of uncertainty. SHAP analysis was also employed to identify the contribution of different input features to the model outputs, thereby improving the interpretability of the prediction results. The SBLOCA case study shows that the model incorporating dimensionless physical parameters improves both prediction accuracy and uncertainty performance compared with the model without dimensionless parameters. The results of mean squared error, root mean squared error, mean absolute error, and mean absolute percentage error measures are 21.995, 4.690, 1.957, and 3.171%, respectively. Compared with the approximately 30 min computational time required by a single RELAP5 simulation, the proposed surrogate model reduces the inference time for a complete accident sequence to (355.778±12.521) ms, significantly improving computational efficiency. The uncertainty evaluation results show that the global average IS of the physics-enhanced model is 9.16, which is 27.8% lower than that of the model without dimensionless parameters. The SHAP analysis indicates that core water level and break area are important factors affecting PCT prediction, while dimensionless parameters such as Re, Pr, and Nu at the hot spot also contribute to the prediction. These results suggest that incorporating appropriate physical mechanism parameters can improve the accuracy, efficiency, and interpretability of data-driven surrogate models under complex accident conditions, providing a useful reference for rapid prediction of safety-critical parameters and auxiliary safety-state assessment in nuclear power plants.

     

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