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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 |
ISSN | 0253-3219 |
卷号 | 46期号:11 |
发表状态 | 已发表 |
DOI | 10.11889/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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