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Zhu Yong, Han Tonghang, Ren Hongbing. Analysis of Effect of Steam Generator Anti-Vibration Bars Shift on Flow Induced Vibration and Wear of Tube Bundle[J]. Nuclear Power Engineering, 2016, 37(5): 29-32. doi: 10.13832/j.jnpe.2016.05.0029
Citation: Zhu Yong, Han Tonghang, Ren Hongbing. Analysis of Effect of Steam Generator Anti-Vibration Bars Shift on Flow Induced Vibration and Wear of Tube Bundle[J]. Nuclear Power Engineering, 2016, 37(5): 29-32. doi: 10.13832/j.jnpe.2016.05.0029

Analysis of Effect of Steam Generator Anti-Vibration Bars Shift on Flow Induced Vibration and Wear of Tube Bundle

doi: 10.13832/j.jnpe.2016.05.0029
  • Received Date: 2015-11-23
  • Rev Recd Date: 2015-12-20
  • Available Online: 2025-02-15
  • During the pre-service eddy current inspection(PSI) of the steam generator of a power station, it was determined that the anti-vibration bars(AVBs) No.3 shifted from the design location to the cold side by approximately 10 degrees. Based on the specific flow induced analysis program GERBOISE, flow elastic characteristic, turbulence excitation response and fretting wear of the tube bundle for both AVBs design and shifted locations are calculated. By comparison of the calculated results of design and shifted conditions, the effects of AVBs shift on flow induced vibration and fretting wear are evaluated. The evaluated conclusion is that the shifted AVBs will not lead to the unaccepted flow induced vibration response and excessive fretting wear for the heat transfer tube.

     

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      沈阳化工大学材料科学与工程学院 沈阳 110142

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