Development and validation of machine learning-based transient identification models in a liquid-fueled molten salt reactor system
2023-12-15
发表期刊NUCLEAR ENGINEERING AND DESIGN (IF:1.9[JCR-2023],2.0[5-Year])
ISSN0029-5493
卷号415
发表状态已发表
DOI10.1016/j.nucengdes.2023.112682
摘要

Safety is the most important aspect of nuclear power plants. Rapid identification and effective prevention of accidents in nuclear reactor system is a significant method to enhance the safety of the current fleet of reactors. Machine learning (ML) has been introduced in engineering applications of nuclear power plants and is becoming increasingly practical and powerful in recent years. Consequently, ML can also benefit rapid transient identification in nuclear power plants. The feasibility of ML-based identification models to identify transient events in liquid-fueled Molten Salt Reactor (MSR) is presented. Four transient identification models based on recurrent neural network (RNN), support vector machine (SVM), decision tree (DT) and k-nearest neighbor (KNN) were developed and validated. RELAP5-TMSR code was used to generate datasets including eleven operation conditions, and these datasets were used to train, optimize, and validate the identification models. Four metrics including accuracy, precision, recall and F1 score were utilized to evaluate all four identification models. Moreover, the robustness of the models under noise was tested. The four ML-based models were successfully applied to transient identification of liquid-fueled MSRs. The KNN-based model has the best performance and achieves high test scores under noise. In the future, these proposed intelligent identification models will have good potential and prospects in supporting the operation of nuclear power plants. © 2023 Elsevier B.V.

关键词Decision trees Learning systems Nearest neighbor search Nuclear energy Nuclear fuels Nuclear reactor accidents Recurrent neural networks Support vector machines 'current Engineering applications Identification modeling Machine-learning Nuclear reactor systems Nuclear safety Prevention of accidents Rapid identification Reactor systems Transient identification
收录类别SCI ; EI
语种英语
出版者Elsevier Ltd
EI入藏号20234214910415
EI主题词Nuclear power plants
EI分类号613 Nuclear Power Plants ; 723 Computer Software, Data Handling and Applications ; 914.1 Accidents and Accident Prevention ; 921.4 Combinatorial Mathematics, Includes Graph Theory, Set Theory ; 921.5 Optimization Techniques ; 932.2 Nuclear Physics ; 961 Systems Science
原始文献类型Journal article (JA)
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文献类型期刊论文
条目标识符https://kms.shanghaitech.edu.cn/handle/2MSLDSTB/340977
专题物质科学与技术学院_硕士生
物质科学与技术学院_特聘教授组_戴志敏组
通讯作者Cheng, Maosong
作者单位
1.ShanghaiTech University, Shanghai; 201210, China;
2.Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai; 201800, China;
3.University of Chinese Academy of Sciences, Beijing; 100049, China
第一作者单位上海科技大学
第一作者的第一单位上海科技大学
推荐引用方式
GB/T 7714
Zhou, Tianze,Yu, Kaicheng,Cheng, Maosong,et al. Development and validation of machine learning-based transient identification models in a liquid-fueled molten salt reactor system[J]. NUCLEAR ENGINEERING AND DESIGN,2023,415.
APA Zhou, Tianze,Yu, Kaicheng,Cheng, Maosong,Li, Rui,&Dai, Zhimin.(2023).Development and validation of machine learning-based transient identification models in a liquid-fueled molten salt reactor system.NUCLEAR ENGINEERING AND DESIGN,415.
MLA Zhou, Tianze,et al."Development and validation of machine learning-based transient identification models in a liquid-fueled molten salt reactor system".NUCLEAR ENGINEERING AND DESIGN 415(2023).
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