Affiliation:
1. Korea Electric Power Research Institute
2. Korea Electric Power Research Institute (KEPRI)
Abstract
For developing fatigue design curve of cast stainless steel that is used in piping material
of nuclear power plants, a low-cycle fatigue test rig was built. It is capable of performing tests in
pressurized high temperature water environment of PWR. Cylindrical solid fatigue specimens of
CF8M were used for the strain-controlled environmental fatigue tests. Fatigue life was measured in
terms of the number of cycles with the variation of strain amplitude at 0.04%/s strain rates. The
disparity between target length and measured length of specimens was corrected by using finite
element method. The corrected test results showed similar fatigue life trend with other previous
results.
Publisher
Trans Tech Publications, Ltd.
Subject
Mechanical Engineering,Mechanics of Materials,General Materials Science
Reference9 articles.
1. Y.S. Garud, et. al.: Corrosion Fatigue of Water-Touched Pressure Retaining Components in Power Plants, EPRI TR-106696 (1997).
2. D.A. Gerber: Evaluation of Environmental Fatigue Effects for a Westinghouse Nuclear Power Plant, EPRI TR-110043 (1998).
3. Chopra: Overview of Fatigue Crack Initiation in Carbon and Low-Alloy Steels in Light Water Reactor Environments, Journal of Pressure Vessel and Technology Vol. 121 (1999).
4. M. Itatani, et. al: Fatigue Crack Growth Curve for Austenitic Stainless Steels in BWR Environment, Journal of Pressure Vessel and Technology Vol. 123 (2001).
5. W. E. Ruther, et. al: Environmentally Assisted Cracking in Light Water Reactors, NUREG/CR4667, Vol. 15 (1993).
Cited by
1 articles.
订阅此论文施引文献
订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献