Development and analysis of a K-nearest-neighbor-based transient identification model for molten salt reactor systems
2023
发表期刊HE JISHU/NUCLEAR TECHNIQUES
ISSN0253-3219
卷号46期号:11
发表状态已发表
DOI10.11889/j.0253-3219.2023.hjs.46.110604
摘要

[Background] Molten salt reactors (MSRs) are fourth-generation advanced nuclear energy systems that exhibit characteristics such as high safety, high economy, nonproliferation, and sustainability. To ensure the safe operation of MSRs, identifying transient conditions promptly and accurately is crucial. However, current system transient identification methods rely on manual identification by operators, introducing significant human factors seriously affecting nuclear power safety. [Purpose] This study aims to establish a transient identification model for an MSR system based on the K-nearest neighbor (KNN) method, so as to reduce human factors introduced during the traditional system transient identification process, and improve the operational safety of the MSR. [Methods] Datasets for the system transient identification model were generated by using the RELAP5-TMSR code to simulate 11 operating conditions of the molten salt reactor experiment (MSRE) built and operated at Oak Ridge National Laboratory in the United States. Subsequently, a system transient identification model based on the KNN method was developed by training, optimizing, and validating these datasets. Four metrics, i.e., accuracy, precision, recall, and F1-score were applied to evaluating the system transient identification model. Finally, the robustness of the model was tested and optimized under noisy conditions. [Results] The results demonstrate that the KNN-based transient identification model for the MSR system achieves a 99.99% F1-score on the test datasets. The system transient identification model also exhibits high robustness, with an F1-score of 94.32% under noisy conditions. The optimized system transient identification model achieves a 99.73% F1-score when identifying transient conditions under noise, accurately identifying the transient conditions of the MSRE. [Conclusions] The KNN-based transient identification model for the MSR system can satisfy the requirements of transient identification of the MSR system, hence be applied to intelligent MSR operations and maintenance, ensuring safe MSR operation. © 2023 Science Press. All rights reserved.

关键词Fused salts Human engineering Man machine systems Molten salt reactor Motion compensation Nearest neighbor search Nuclear power plants F1 scores Identification modeling K-near neighbor Nearest-neighbour Reactor systems Robustness System transient identification System transients Transient conditions Transient identification
收录类别EI
语种中文
出版者Science Press
EI入藏号20234915160146
EI主题词Nuclear fuels
EI分类号461.4 Ergonomics and Human Factors Engineering ; 613 Nuclear Power Plants ; 621.1 Fission Reactors ; 804.2 Inorganic Compounds ; 921.5 Optimization Techniques
原始文献类型Journal article (JA)
文献类型期刊论文
条目标识符https://kms.shanghaitech.edu.cn/handle/2MSLDSTB/348678
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; Dai, Zhimin
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
通讯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 analysis of a K-nearest-neighbor-based transient identification model for molten salt reactor systems[J]. HE JISHU/NUCLEAR TECHNIQUES,2023,46(11).
APA Zhou, Tianze,Yu, Kaicheng,Cheng, Maosong,&Dai, Zhimin.(2023).Development and analysis of a K-nearest-neighbor-based transient identification model for molten salt reactor systems.HE JISHU/NUCLEAR TECHNIQUES,46(11).
MLA Zhou, Tianze,et al."Development and analysis of a K-nearest-neighbor-based transient identification model for molten salt reactor systems".HE JISHU/NUCLEAR TECHNIQUES 46.11(2023).
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