Environmental Fatigue Crack Propagation Behavior of Cast Stainless Steels under PWR Condition

Author:

Jeong Ill Seok1,Kim Sang Jai1,Song Taek Ho1,Kwon Jong Jooh,Hong Sung Yul,Cho Sun Young

Affiliation:

1. Korea Electric Power Research Institute

Abstract

Environmental fatigue crack propagation of CF8M and CF8A steels used in the domestic nuclear power plants (NPPs) were investigated on the simulated pressurized water reactor (PWR) condition (temperature: 316°C, pressure: 15MPa). The test equipment for environmental fatigue (high temperature-high pressure loop, autoclave, load frame, and measurement system) was designed. As-received and 60-year aged specimens were used in the test. To compare with environmental fatigue test, another test in the air condition was performed. The fracture surfaces of specimens were difficult to verify the fracture modes such as striation, inter-granular crack and cleavage and so on. As the ferrite content of CF8M is increased, more particles on the fracture surface were peeled.

Publisher

Trans Tech Publications, Ltd.

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference8 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. O.K. Chopra: Overview of Fatigue Crack Initiation in Carbon and Low-Alloy Steels in Light Water Reactor Environments, J. Pres. Ves. Tech. Vol. 121 (1999).

4. M. Itatani, et. al: Fatigue Crack Growth Curve for Austenitic Stainless Steels in BWR Environment, J. Pres. Ves. Tech. Vol. 123 (2001).

5. W.E. Ruther et. al: Environmentally Assisted Cracking in Light Water Reactors, NUREG/ CR-4667, Vol. 15 (1993).

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