Assembly-oriented reliability analysis method for the top-connection structure of a nuclear fuel assembly

被引：2
作者：
Liu, Ying-Dong [1 ,2 ]
Li, Wen-Qiang [1 ,2 ]
Chen, Jia-Hao [1 ,2 ]
Ling, Si-Tong [1 ,2 ]
Wan, Chang-Fu [1 ,2 ]
机构：
[1] Sichuan Univ, Sch Mech Engn, Chengdu 610065, Peoples R China
[2] Innovat Method & Creat Design Key Lab Sichuan Prov, Chengdu 610065, Peoples R China
来源：
NUCLEAR SCIENCE AND TECHNIQUES | 2023年 / 34卷 / 06期
基金：
中国国家自然科学基金;
关键词：
Assembly; Top-connection structure; Parametric model; Approximation model; Structural reliability; SIMULATION; DESIGN; IMPACT;
D O I：
10.1007/s41365-023-01247-7
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
The nuclear fuel assembly is the core component of a nuclear reactor. In a pressurized water reactor fuel assembly, the top-connection structure connects the top nozzle to the guide thimble. Its performance reliability is essential for the stability of the nuclear fuel assembly. In this study, an assembly-oriented reliability analysis method for top-connection structures is presented by establishing an assembly-oriented top-connection structure parameter modeling method and a nonlinear contact gap and penetration correction method. A reliability model of the top-connection assembly structure, including multiple stochastic design variables, was constructed, and the overall reliability of the top-connection assembly structure was obtained via a Kriging model and Monte Carlo simulation. The acquired experimental data were consistent with real-world failure conditions, which verified the practicability and feasibility of the reliability analysis method proposed in this study.
引用
收藏
页数：16
相关论文
共 34 条
[31]   Trends and needs in experimentation and numerical simulation for LWR safety [J].
Yadigaroglu, G ;
Andreani, M ;
Dreier, J ;
Coddington, P .
NUCLEAR ENGINEERING AND DESIGN, 2003, 221 (1-3) :205-223
[32]   Finite element analysis of the mechanical behavior of a nuclear fuel assembly spacer grid [J].
Yoo, Youngik ;
Kim, Kyounghong ;
Eom, Kyongbo ;
Lee, Seongki .
NUCLEAR ENGINEERING AND DESIGN, 2019, 352
[33]   CFD investigation of the cold wall effect on CHF in a 5 x 5 rod bundle for PWRs [J].
Zhang, Ji ;
Wang, Mingjun ;
Chen, Chong ;
Tian, Wenxi ;
Qiu, Suizheng ;
Su, G. H. .
NUCLEAR ENGINEERING AND DESIGN, 2022, 387
[34]  
Zhao J., 2022, INT C NUCL ENG, V86366, DOI [10.1115/ICONE29-91931, DOI 10.1115/ICONE29-91931]
1234