{"title":"压水堆事故预测中定量参数重要性和运行阈值的可解释机器学习","authors":"Jinqi Zheng, Yichun Wu, Qing Liang, Jiale Ling, Jiayan Fang","doi":"10.1016/j.pnucene.2025.105948","DOIUrl":null,"url":null,"abstract":"<div><div>The \"black box\" nature of machine learning models hinders trust and transparency in nuclear safety systems, where interpretability is critical. This study introduces an explainable CatBoost-SHAP framework for accident prediction in pressurized water reactors (PWRs). Leveraging CPR1000 reactor simulator and Optuna-optimized CatBoost, the model achieved high accuracy (R<sup>2</sup> > 0.999, MAPE <1 %) on small break loss-of-coolant accident (SBLOCA) datasets for both hot-leg and cold-leg scenario, outperforming XGBoost and LightGBM. SHAP analysis identified key thermal-hydraulic drivers (e.g., steam generator (SG) pressure <6.74 MPa, wide-range downcomer level <−1.4 %) and uncovered nonlinear interactions among multi-loop variables, consistent with reactor physics. The framework's dual capability - high predictive precision and mechanistic interpretability - enables operators to validate decision pathways and prioritize safety thresholds. By bridging the gap between opaque AI and nuclear safety demands, this work provides practical guidelines for real-time diagnostics and proactive accident mitigation in PWRs.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"189 ","pages":"Article 105948"},"PeriodicalIF":3.2000,"publicationDate":"2025-07-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Interpretable machine learning for quantitative parameter importance and operational thresholds in PWR accident prediction\",\"authors\":\"Jinqi Zheng, Yichun Wu, Qing Liang, Jiale Ling, Jiayan Fang\",\"doi\":\"10.1016/j.pnucene.2025.105948\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>The \\\"black box\\\" nature of machine learning models hinders trust and transparency in nuclear safety systems, where interpretability is critical. This study introduces an explainable CatBoost-SHAP framework for accident prediction in pressurized water reactors (PWRs). Leveraging CPR1000 reactor simulator and Optuna-optimized CatBoost, the model achieved high accuracy (R<sup>2</sup> > 0.999, MAPE <1 %) on small break loss-of-coolant accident (SBLOCA) datasets for both hot-leg and cold-leg scenario, outperforming XGBoost and LightGBM. SHAP analysis identified key thermal-hydraulic drivers (e.g., steam generator (SG) pressure <6.74 MPa, wide-range downcomer level <−1.4 %) and uncovered nonlinear interactions among multi-loop variables, consistent with reactor physics. The framework's dual capability - high predictive precision and mechanistic interpretability - enables operators to validate decision pathways and prioritize safety thresholds. By bridging the gap between opaque AI and nuclear safety demands, this work provides practical guidelines for real-time diagnostics and proactive accident mitigation in PWRs.</div></div>\",\"PeriodicalId\":20617,\"journal\":{\"name\":\"Progress in Nuclear Energy\",\"volume\":\"189 \",\"pages\":\"Article 105948\"},\"PeriodicalIF\":3.2000,\"publicationDate\":\"2025-07-29\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Progress in Nuclear Energy\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0149197025003464\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Progress in Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0149197025003464","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
Interpretable machine learning for quantitative parameter importance and operational thresholds in PWR accident prediction
The "black box" nature of machine learning models hinders trust and transparency in nuclear safety systems, where interpretability is critical. This study introduces an explainable CatBoost-SHAP framework for accident prediction in pressurized water reactors (PWRs). Leveraging CPR1000 reactor simulator and Optuna-optimized CatBoost, the model achieved high accuracy (R2 > 0.999, MAPE <1 %) on small break loss-of-coolant accident (SBLOCA) datasets for both hot-leg and cold-leg scenario, outperforming XGBoost and LightGBM. SHAP analysis identified key thermal-hydraulic drivers (e.g., steam generator (SG) pressure <6.74 MPa, wide-range downcomer level <−1.4 %) and uncovered nonlinear interactions among multi-loop variables, consistent with reactor physics. The framework's dual capability - high predictive precision and mechanistic interpretability - enables operators to validate decision pathways and prioritize safety thresholds. By bridging the gap between opaque AI and nuclear safety demands, this work provides practical guidelines for real-time diagnostics and proactive accident mitigation in PWRs.
期刊介绍:
Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field.
Please note the following:
1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy.
2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc.
3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.