Fretting wear between Alloy 690 and 405 stainless steel in high temperature pressurized water with different normal force and displacement-Reference-Cited by-同舟云学术

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Fretting wear between Alloy 690 and 405 stainless steel in high temperature pressurized water with different normal force and displacement

Published:2020-02 Issue: Volume:529 Page:151930
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Ming Hongliang,Liu Xingchen,Lai Jiang,Wang Jianqiu,Gao Lixia,Han En-Hou

Funder

Natural Science Foundation of Liaoning Province

Institute of Metal Research, Chinese Academy of Sciences, China

National Natural Science Foundation of China

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference39 articles.

1. Effect of temperature on corrosion behavior of alloy 690 in high temperature hydrogenated water;Wang;J. Mater. Sci. Technol.,2018

2. Stress corrosion cracking of alloy 600 &690 steam generator tubing;Sherburne,2009

3. Vibration analysis of shell-and-tube heat exchangers: an overview—Part 2: vibration response, fretting-wear, guidelines;Pettigrew;J. Fluids Struct.,2003

4. Flow-induced vibration and wear of steam generator tubes;Connors;Nucl. Technol.,2017

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1. Effects of excitation parameters on fretting wear and corrosion of 316L stainless steel under random impact-sliding condition;Wear;2024-12

2. Effect of CrAlTiN Coating on Fretting Wear Behavior of Inconel 690 Alloy in Dry and Seawater Conditions;Journal of Materials Engineering and Performance;2024-08-26

3. Comparison and correlation between sinusoidal fretting and random fretting of Zr-4 alloy tube;Tribology International;2024-05

4. Effects of displacement amplitude and normal force on fretting wear behavior of zirconium alloy tube in simulated primary water of PWR;Wear;2024-04

5. Investigation on the failure mechanistic evolution of fretting corrosion of Alloy 690 with increasing cycles in high-temperature water;Journal of Nuclear Materials;2024-04

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