Abstract

Although reference fatigue crack growth curves for austenitic stainless steels in air environments and boiling water reactor (BWR) environments were prescribed in JSME S NA1-2002, similar curves for pressurized water reactors (PWR) were not prescribed. In order to propose the reference curve in PWR environment, fatigue tests of austenitic stainless steels in simulated PWR primary water environment were carried out. According to the procedure to determine the reference fatigue crack growth curve of BWR, which of PWR is proposed. The reference fatigue crack growth curve in PWR environment have been determines as a function of stress intensity factor range, Temperature, load rising time and stress ratio.

Keywords:
Pressurized water reactor Materials science Austenite Austenitic stainless steel Paris' law Boiling water reactor Metallurgy Corrosion fatigue Stress (linguistics) Stress intensity factor Light-water reactor Boiling Nuclear reactor Crack closure Structural engineering Nuclear engineering Fracture mechanics Composite material Corrosion Engineering Microstructure Thermodynamics

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22
Cited By
1.28
FWCI (Field Weighted Citation Impact)
4
Refs
0.79
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Is in top 1%
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Citation History

Topics

Fatigue and fracture mechanics
Physical Sciences →  Engineering →  Mechanics of Materials
Engineering Applied Research
Physical Sciences →  Engineering →  Civil and Structural Engineering
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