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Author:

Liao, Haoyu (Liao, Haoyu.) | Wang, Yangyang (Wang, Yangyang.) | Li, Yuanming (Li, Yuanming.) | Wang, Kunpeng (Wang, Kunpeng.) | Deng, Yangbin (Deng, Yangbin.) | Su, Min (Su, Min.) | Wu, Yingwei (Wu, Yingwei.) | Wang, Mingjun (Wang, Mingjun.) | Qiu, Suizheng (Qiu, Suizheng.)

Indexed by:

EI SCIE Scopus Engineering Village

Abstract:

In this study, a three-dimensional (3D) fluid-solid coupling simulation with the full consideration of irradiation effects for plate-type nuclear fuel assemblies was conducted. Mechanical models of radiation-induced deformations in solid domain and thermo-hydraulic models in fluid domain were established based on ABAQUS and FLUENT, respectively. By use of MpCCI, the capability of fluid-solid coupling simulation was developed through the real-time parameter exchange of different physical fields at fluid-solid boundary interfaces. The accuracy and reliability of fluid-solid coupling methodology by FLUENT-MpCCI-ABAQUS was validated through benchmark with simulation in public reference. The influence of radiation swelling and bending deformation on fluid thermal-hydraulic characteristics was investigated based on the developed coupling analysis method. In addition, the sensitivity study of heterogeneous swelling and flow channel width was carried out. The simulation result shows that radiation swelling and bending deformation exerted substantial influence on flow distribution and outlet temperature. © 2020 Elsevier Ltd

Keyword:

Channel flow Deformation Hydraulic models Irradiation Nuclear fuels

Author Community:

  • [ 1 ] [Liao, Haoyu]School of Nuclear Science and Technology, Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an; 710049, China
  • [ 2 ] [Wang, Yangyang]School of Nuclear Science and Technology, Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an; 710049, China
  • [ 3 ] [Li, Yuanming]Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu; 610213, China
  • [ 4 ] [Wang, Kunpeng]Nuclear and Radiation Safety Center, Ministry of Ecology and Environment of the People's Republic of China, Beijing; 100082, China
  • [ 5 ] [Deng, Yangbin]College of Physics and Optoelectronic Engineering, Shenzhen University, Shenzhen; 518060, China
  • [ 6 ] [Su, Min]Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu; 610213, China
  • [ 7 ] [Wu, Yingwei]School of Nuclear Science and Technology, Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an; 710049, China
  • [ 8 ] [Wang, Mingjun]School of Nuclear Science and Technology, Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an; 710049, China
  • [ 9 ] [Qiu, Suizheng]School of Nuclear Science and Technology, Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an; 710049, China

Reprint Author's Address:

  • [Deng, Yangbin]College of Physics and Optoelectronic Engineering, Shenzhen University, Shenzhen; 518060, China;;

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Source :

Progress in Nuclear Energy

ISSN: 0149-1970

Year: 2020

Volume: 126

2 . 2 5 6

JCR@2020

2 . 2 5 6

JCR@2020

ESI Discipline: ENGINEERING;

ESI HC Threshold:59

CAS Journal Grade:3

Cited Count:

WoS CC Cited Count: 5

SCOPUS Cited Count: 14

ESI Highly Cited Papers on the List: 0 Unfold All

WanFang Cited Count:

Chinese Cited Count:

30 Days PV: 5

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