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Experimental investigation of impact-sliding interaction and fretting wear between tubes and anti-vibration bars in steam generators

  • Published:2020-06 Issue:6 Volume:52 Page:1304-1317
  • ISSN:1738-5733
  • Container-title:Nuclear Engineering and Technology
  • language:en
  • Short-container-title:Nuclear Engineering and Technology

Author:

Guo Kai,Jiang Naibin,Qi Huanhuan,Feng Zhipeng,Wang Yang,Tan Wei

Funder

Science and Technology on Nuclear Reactor System Design Technology Laboratory, Nuclear Power Institute of China

National Natural Science Foundation of China

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference27 articles.

1. Flow-induced vibration: recent findings and open questions;Taylor;Nucl. Eng. Des.,1998

2. Experimental study of impact forces in multi-span PWR steam generator tubes;Axisa,1984

3. Cross-flow-induced chaotic vibrations of heat-exchanger tubes impacting on loose supports;Païdoussis;J. Sound Vib.,1992

4. Intermittency transition to chaos in the response of a loosely supported cylinder in an array in cross-flow;Mureithi;Chaos, Solit. Fractals,1995

5. Fretting wear of heat exchanger tubes—Part I experiments;Blevins;J. Eng. Power Trans. ASME,1979
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