Nuclear Techniques ›› 2020, Vol. 43 ›› Issue (1): 10602-010602.doi: 10.11889/j.0253-3219.2020.hjs.43.010602

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Acoustic finite element method for dynamic response analysis of reactor internals induced by loss-of-coolant accident

Xielin ZHAO1,Yingchao MA1,Xianhui YE2,Naibin JIANG2,Jinxiong ZHOU1()   

  1. 1. State Key Laboratory for Strength and Vibration of Mechanical Structures, School of Aerospace, Xi’an Jiaotong University, Xi’an 710049, China
    2. Key Laboratory of Nuclear Reactor System Design Technology, Nuclear Power Institute of China, Chengdu 610200, China
  • Received:2019-07-18 Revised:2019-11-28 Online:2020-01-15 Published:2020-01-21
  • Contact: Jinxiong ZHOU
  • About author:ZHAO Xielin, male, born in 1994, graduated from Xi'an Jiaotong University in 2017, master student
  • Supported by:
    National Natural Science Foundation of China(11872060)

Abstract: Background

Dynamic response of reactor internals due to loss-of-coolant accident (LOCA) is one of the main issues in structural dynamics of nuclear reactors. Current analysis methods mainly adopt computation fluid dynamics (CFD) based fluid-structure interaction approaches, which have high numerical accuracy but pay the price of high computational cost.


This study aims to propose acoustic finite element method for dynamic analysis of reactor internals induced by loss-of-coolant accident.


Displacements of both fluid and structure and the pressure of fluid were taken as basic unknown variables in this flow acoustic finite element method. The commercial code, ADINA, together with conforming mesh along the fluid-structure interface, was utilized to model the V32 experiment of the Germany HDR (Heiss Dampf Reaktor) reactor.


The acoustic-structure coupling results agree well with the experimental results reported in reference and the results given by CFD-based two-way coupling method whilst relative lower computation cost and ease implementation are achieved.


The study provides a straightforward and efficient method for engineering nuclear LOCA dynamic analysis.

Key words: LOCA, Reactor internals, Dynamic response, Fluid-structure interaction, Acoustic finite element

CLC Number: 

  • TL334