The fatigue life of austenitic stainless steel has recently been shown to undergo remarkable reduction with decrease in strain rate and increase in temperature in water. Either of these parameters as a factor of this reduction has been examined quantitatively and methods for predicting the fatigue life reduction factor Fen in any given set of conditions have been proposed. All these methods are based primarily on fatigue data in simulated PWR water owing to the few data available in simulated BWR water. Recent Japanese fatigue data in simulated BWR water clearly indicated the effects of the environment on fatigue degradation to be milder than under actual PWR conditions. A new method for determining Fen in BWR water was developed in the present study and a revised Fen in PWR water is also proposed based on new data. These new models differ from those previously used primarily with regard to the manner in which strain amplitude is considered to affect Fen in the environment.

Issue Section:
Technical Papers
Keywords:
austenitic stainless steel, fatigue testing, stress-strain relations, fission reactor materials, fission reactor safety, fission reactor design, fission reactor cooling
Topics:
Boiling water reactors, Fatigue, Fatigue life, Pressurized water reactors, Stainless steel, Water, Temperature
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