Recent research efforts have focused on characterizing the effects of light water reactor environments on the fatigue behavior of austenitic stainless steels. In conjunction with these experimental programs, there has been a significant effort at Argonne National Laboratory to develop statistical models for predicting the fatigue behavior of austenitic stainless steels in air and water environments at prototypical temperatures and loading rates. Some recent testing has also been concerned with the effect of mean stress on the fatigue behavior of 304 stainless steel in air. The ultimate goal of all these efforts is to allow development of fatigue design curves and design procedures that will assure adequate margin to fatigue crack initiation...
In this paper, the low cycle fatigue resistance of a 304L austenitic stainless steel in a simulated ...
Fatigue is a major degradation mechanism and life-limiting factor for primary circuit piping. High t...
The existing fatigue strain versus life (S-N) data for materials used in nuclear power plant compon...
A statistical model for austenitic stainless steels for predicting the effect of pressurized water r...
Fatigue life tests were performed in air on Type 304 stainless steel (304 SS) to establish the effec...
The ASME Boiler and Pressure Vessel Code fatigue design curves for structural materials do not expli...
The fatigue life design curves in nuclear codes are generally derived from uniaxial straincontrolled...
Fatigue tests have been conducted on Types 304 and 316NG stainless steels to evaluate the effects of...
The first results of a detailed fatigue model for austenitic stainless steels in general and for the...
A statistical model for austenitic stainless steels (SSs) for predicting the effect of boiling water...
Austenitic stainless steels is used in many components of nuclear power plants, particularly in the ...
This paper summarizes the work performed at Argonne National Laboratory on the fatigue of piping and...
International audienceA substantial amount of research effort has been applied to the field of envir...
The update of the ASME III design fatigue curve for stainless steel in conjunction with the Fen mode...
Mean stress effects on fatigue life of a stainless steel in air and boiling water reactor (BWR) envi...
In this paper, the low cycle fatigue resistance of a 304L austenitic stainless steel in a simulated ...
Fatigue is a major degradation mechanism and life-limiting factor for primary circuit piping. High t...
The existing fatigue strain versus life (S-N) data for materials used in nuclear power plant compon...
A statistical model for austenitic stainless steels for predicting the effect of pressurized water r...
Fatigue life tests were performed in air on Type 304 stainless steel (304 SS) to establish the effec...
The ASME Boiler and Pressure Vessel Code fatigue design curves for structural materials do not expli...
The fatigue life design curves in nuclear codes are generally derived from uniaxial straincontrolled...
Fatigue tests have been conducted on Types 304 and 316NG stainless steels to evaluate the effects of...
The first results of a detailed fatigue model for austenitic stainless steels in general and for the...
A statistical model for austenitic stainless steels (SSs) for predicting the effect of boiling water...
Austenitic stainless steels is used in many components of nuclear power plants, particularly in the ...
This paper summarizes the work performed at Argonne National Laboratory on the fatigue of piping and...
International audienceA substantial amount of research effort has been applied to the field of envir...
The update of the ASME III design fatigue curve for stainless steel in conjunction with the Fen mode...
Mean stress effects on fatigue life of a stainless steel in air and boiling water reactor (BWR) envi...
In this paper, the low cycle fatigue resistance of a 304L austenitic stainless steel in a simulated ...
Fatigue is a major degradation mechanism and life-limiting factor for primary circuit piping. High t...
The existing fatigue strain versus life (S-N) data for materials used in nuclear power plant compon...