Nuclear Science and Techniques ›› 2019, Vol. 42 ›› Issue (4): 40603-040603.doi: 10.11889/j.0253-3219.2019.hjs.42.040603

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Study on sloshing response characteristics of liquid heavy metal coolant

Xuemin WU1,2,Yong ZHANG1(),Meisheng HE1,Jieqiong JIANG1   

  1. 1. Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Safety Technology, Chinese Academy of Sciences, Hefei 230031, China
    2. University of Science and Technology of China, Hefei 230026, China
  • Received:2019-01-16 Revised:2019-03-06 Online:2019-04-10 Published:2019-04-18
  • Contact: Yong ZHANG E-mail:yong.zhang@fds.org.cn
  • About author:<named-content content-type="corresp-name">WU Xuemin</named-content>, male, born in 1990, graduated from the Engineering & Technical College of Chengdu University of Technology in 2015, master student, focusing on nuclear reactor structural safety|<named-content content-type="corresp-name">WU Xuemin</named-content>, male, born in 1990, graduated from the Engineering & Technical College of Chengdu University of Technology in 2015, master student, focusing on nuclear reactor structural safety|ZHANG Yong, E-mail: <email>yong.zhang@fds.org.cn</email>
  • Supported by:
    Supported by National Natural Science Foundation of China (No.51408585, No.11772086), Natural Science Foundation of Anhui Province of China(No.1608085ME113)

Abstract: Background

Compared with the traditional pressurized-water reactor (PWRs) with low density coolant and loop layout, the lead-based reactor uses liquid heavy metal coolant and has the characteristics of pool layout.

Purpose

This study aims at the impact and vibration modes of heavy metal coolant’s sloshing to the reactor vessel and its internal components under a load of seismic.

Methods

First of all, two-way fluid-structure coupling finite element method was applied to the seismic response analysis of liquid heavy metal reactor. Then the sloshing effect of coolant type, the support form, as well as the height-diameter ratio on the sloshing effect of coolant in the reactor container, were calculated and analyzed.

Results

The calculation results show that the seismic response of liquid heavy metals is not equal to that of light coolant, and the fluid-dynamic viscosity is not significant for fluid-solid coupling of large-scale reactors. The different support forms have stress concentration at the support position and the overall performance is that the beam mode is not sensitive to the support form. The vibration modes stimulated by different liquid-filled ratios are similar, and the smaller the liquid-filled ratio, the more concentrated the maximum stress intensity point are on the bottom head.

Conclusion

These results provide a parametric basis for the structural safety design of liquid heavy metal reactors.

Key words: Liquid heavy metal reactor, Coolant sloshing, Pool structure, Seismic response, Fluid-structure interaction

CLC Number: 

  • TL334