Progress in studying the fretting wear/corrosion of nuclear steam generator tubes
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference98 articles.
1. The effects of ultrasonic nanocrystal surface modification temperature on the mechanical properties and fretting wear resistance of Inconel 690 alloy;Amanov;Appl. Surf. Sci.,2018
2. ASTM, 2009. Standard guide for determining synergism between wear and corrosion. G119-09.
3. ASTM, 2010. Standard test method for damage to contacting solid surfaces under fretting conditions. G204-10.
4. Fretting fatigue and wear damage of structural components in nuclear power stations-fitness for service and life management perspective;Attia;Tribol. Int.,2006
5. On the thermal origin of the antagonistic and synergistic effects of fretting and crevice corrosion processes in multi-phase flow environment;Attia;Tribol. Int.,2009
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1. A cumulative damage model for tubes in nuclear power plants subject to continuous degradation and multi-effect shocks under dynamic environments;Annals of Nuclear Energy;2024-12
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3. Role of various influencing parameters on high temperature fretting behaviour of different tribopairs in liquid lead;Nuclear Materials and Energy;2024-09
4. Effect of fretting wear regimes on stress corrosion cracking of Alloy 690TT in high-temperature pressurized water;Corrosion Science;2024-08
5. Influence of Chloride Concentration on Fretting Wear Behavior of Inconel 600 Alloy;Materials;2024-06-17
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