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Uncertainty quantification of the power control system of a small PWR with coolant temperature perturbation

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成果类型:
期刊论文
作者:
Li, Xiaoyu;Li, Chuhao;Hu, Yang;Yu, Yongqi;Zeng, Wenjie;...
通讯作者:
Wenjie Zeng<&wdkj&>Haibiao Wu
作者机构:
[Li, Xiaoyu; Zeng, Wenjie; Li, Chuhao; Hu, Yang; Wu, Haibiao; Yu, Yongqi] Univ South China, Sch Nucl Sci & Technol, Hengyang City 421001, Peoples R China.
[Wu, Haibiao] Univ South China, Affiliated Hosp 1, Hengyang City 421001, Peoples R China.
通讯机构:
[Wenjie Zeng; Haibiao Wu] S
School of Nuclear Science and Technology, University of South China, Hengyang City, 421001, China<&wdkj&>School of Nuclear Science and Technology, University of South China, Hengyang City, 421001, China<&wdkj&>The First Affiliated Hospital, University of South China, Hengyang City, 421001, China
语种:
英文
关键词:
Uncertainty quantification;Coolant temperature feedback reactivity;Core power control system;Small PWR
期刊:
Nuclear Engineering and Technology
ISSN:
1738-5733
年:
2022
卷:
54
期:
6
页码:
2048-2054
基金类别:
National Natural Science Foundation of China Youth Fund [12005096]; Provincial Innovation and Entrepreneurship Training Program for Undergraduates [S202110555173]
机构署名:
本校为第一机构
院系归属:
核科学技术学院
摘要:
The coolant temperature feedback coefficient is an important parameter of reactor core power control system. To study the coolant temperature feedback coefficient influence on the core power control system of small PWR, the core power control system is built with the nonlinear model and fuzzy control theory. Then, the uncertainty quantification method of reactor core parameters is established based on the Latin hypercube sampling method and the Bootstrap method. Finally, under the conditions of reactivity step perturbation and coolant inlet temperature step perturbation, uncertainty analysis f...

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