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Author:

Weng, Yu (Weng, Yu.) | Wang, Haitao (Wang, Haitao.) | Wang, Haijun (Wang, Haijun.) | Liu, Jialun (Liu, Jialun.) | Pan, Jie (Pan, Jie.) | Deng, Zhian (Deng, Zhian.)

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EI SCIE Scopus Engineering Village

Abstract:

Different from conventional cold leg safety injection, a newly designed reactor type CAP1400 directly connects the injection pipeline of the emergency cooling system with the pressure vessel. However, these structures have been found to potentially have adverse effects on the pressure vessel. This paper employs both physical experiment and numerical analysis to investigate the dynamic oscillating load and the structural response. A 1:9 scale model is adopted for the experimental section. The uncertainty of the measurement quantities is within 3%. The CFD code and the FEM code are used to simulate the transient fluid flow and solid structure deformation, respectively. The sequential coupling method is used for the thermal-fluid-solid coupling calculation. The overall error of the calculation is within ±10%. The result shows that the fluctuation of the physical quantity near the wall is caused by turbulence eddy and thermal mixing, and the flow, heat transfer and structural deformation near the wall of the pressure vessel are closely coupled. The effect of the turbulence eddy can be seen within the entire range of frequency measured, while that of the thermal mixing can be seen only within the low frequency range. The influence law of the loop flow ratio, the flow rate of the downcomer and the loop temperature difference in the structural response are obtained. Through the research of this paper, the law of interaction between the thermal-fluid load and the structural response under direct safety injection is more deeply understood. Thus, it provides a design reference for the safety of reactors. © 2022

Keyword:

Codes (symbols) Computational fluid dynamics Deformation Flow of fluids Heat transfer Mixing Nuclear reactors Pressure vessels Structural design Turbulence Uncertainty analysis

Author Community:

  • [ 1 ] [Weng, Yu]College of Petroleum Engineering, Xi'an Shiyou University, Shaanxi, Xi'an; 710065, China
  • [ 2 ] [Wang, Haitao]School of Mechanical Engineering, Xi'an Jiaotong University, Shaanxi, Xi'an; 710049, China
  • [ 3 ] [Wang, Haijun]State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Shaanxi, Xi'an; 710049, China
  • [ 4 ] [Liu, Jialun]School of Mechanical Engineering, Xi'an Shiyou University, Shaanxi, Xi'an; 710065, China
  • [ 5 ] [Pan, Jie]College of Petroleum Engineering, Xi'an Shiyou University, Shaanxi, Xi'an; 710065, China
  • [ 6 ] [Deng, Zhian]College of Petroleum Engineering, Xi'an Shiyou University, Shaanxi, Xi'an; 710065, China
  • [ 7 ] [Weng, Yu]Xian Shiyou Univ, Coll Petr Engn, Xian 710065, Shaanxi, Peoples R China
  • [ 8 ] [Pan, Jie]Xian Shiyou Univ, Coll Petr Engn, Xian 710065, Shaanxi, Peoples R China
  • [ 9 ] [Deng, Zhian]Xian Shiyou Univ, Coll Petr Engn, Xian 710065, Shaanxi, Peoples R China
  • [ 10 ] [Wang, Haitao]Xi An Jiao Tong Univ, Sch Mech Engn, Xian 710049, Shaanxi, Peoples R China
  • [ 11 ] [Wang, Haijun]Xi An Jiao Tong Univ, State Key Lab Multiphase Flow Power Engn, Xian 710049, Shaanxi, Peoples R China
  • [ 12 ] [Liu, Jialun]Xian Shiyou Univ, Sch Mech Engn, Xian 710065, Shaanxi, Peoples R China

Reprint Author's Address:

  • [Weng, Y.]College of Petroleum Engineering, Shaanxi, China;;

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Source :

Progress in Nuclear Energy

ISSN: 0149-1970

Year: 2022

Volume: 152

2 . 2 5 6

JCR@2020

ESI Discipline: ENGINEERING;

ESI HC Threshold:7

Cited Count:

WoS CC Cited Count:

SCOPUS Cited Count:

ESI Highly Cited Papers on the List: 0 Unfold All

WanFang Cited Count:

Chinese Cited Count:

30 Days PV: 6

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