The response of alloy 690 tubing in a pressurized water reactor environment
Author:
Publisher
Elsevier BV
Subject
Applied Mathematics,General Mathematics
Reference23 articles.
1. Aging and life extension of major light water reactor components;Shah,1993
2. Correlation of Support Impact Force and Fretting-Wear for a Heat Exchanger Tube
3. Vibration Damping in Multispan Heat Exchanger Tubes
4. Steam Generator Fretting-Wear Damage: A Summary of Recent Findings
5. Friction and wear of Inconel 690 and Inconel 600 for steam generator tube in room temperature water
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3. Impact of dynamic strain aging on multiaxial low cycle fatigue behavior of nickel-based alloy 690 at 350 °C;International Journal of Fatigue;2023-05
4. Corrosion fatigue damage mechanism and life evaluation of Inconel Alloy 690TT steam generator tube in high temperature pressurized water;Corrosion Science;2023-03
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