{"title":"Research on severe accident diagnosis method based on PCA and DT for a small modular PWR","authors":"Xiaolong Bi, Peiwei Sun, Xinyu Wei","doi":"10.1016/j.nucengdes.2025.114285","DOIUrl":null,"url":null,"abstract":"<div><div>Small modular pressurized water reactor (SMPWR) is a new trend in the development of nuclear energy today. SMPWRs usually adopt the integrated arrangement and use many passive safety systems, which have high inherent safety. However, despite all precautions, the severe accident (SA) cannot be completely avoided. It is necessary to conduct rapid and timely diagnosis for these SAs. Different from the traditional SA diagnosis methods based on signals and knowledge, the data-based method is adopted to study SA diagnosis of SMPWR in this study. First, the SA state monitoring method based on principal component analysis (PCA) is proposed to realize rapid and accurate distinction between steady-state and abnormal conditions. Then, the SA classification diagnosis method based on decision tree (DT) is proposed to realize accurate diagnosis of initial events and whether the entry conditions of SA management guideline (SAMG) are met. The key parameters selected through feature selection can provide supplement and reference for the selection of monitoring parameters in SAMG and the determination of the instrument list for instrument availability analysis under SA conditions. The fault diagnosis method proposed in this paper can provide the reference and basis for the SA diagnosis and the design of the operator’s SA handling auxiliary system in the SMPWR.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"442 ","pages":"Article 114285"},"PeriodicalIF":1.9000,"publicationDate":"2025-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0029549325004625","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}
引用次数: 0
Abstract
Small modular pressurized water reactor (SMPWR) is a new trend in the development of nuclear energy today. SMPWRs usually adopt the integrated arrangement and use many passive safety systems, which have high inherent safety. However, despite all precautions, the severe accident (SA) cannot be completely avoided. It is necessary to conduct rapid and timely diagnosis for these SAs. Different from the traditional SA diagnosis methods based on signals and knowledge, the data-based method is adopted to study SA diagnosis of SMPWR in this study. First, the SA state monitoring method based on principal component analysis (PCA) is proposed to realize rapid and accurate distinction between steady-state and abnormal conditions. Then, the SA classification diagnosis method based on decision tree (DT) is proposed to realize accurate diagnosis of initial events and whether the entry conditions of SA management guideline (SAMG) are met. The key parameters selected through feature selection can provide supplement and reference for the selection of monitoring parameters in SAMG and the determination of the instrument list for instrument availability analysis under SA conditions. The fault diagnosis method proposed in this paper can provide the reference and basis for the SA diagnosis and the design of the operator’s SA handling auxiliary system in the SMPWR.
期刊介绍:
Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology.
Fundamentals of Reactor Design include:
• Thermal-Hydraulics and Core Physics
• Safety Analysis, Risk Assessment (PSA)
• Structural and Mechanical Engineering
• Materials Science
• Fuel Behavior and Design
• Structural Plant Design
• Engineering of Reactor Components
• Experiments
Aspects beyond fundamentals of Reactor Design covered:
• Accident Mitigation Measures
• Reactor Control Systems
• Licensing Issues
• Safeguard Engineering
• Economy of Plants
• Reprocessing / Waste Disposal
• Applications of Nuclear Energy
• Maintenance
• Decommissioning
Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.