SME Boiler and Pressure Vessel Code provides construction of nuclear power plant components. Figure I-90 Appendix I to Section III of the Code specifies fatigue design curves for structural materials. While effects of environments are not explicitly addressed by the design curves, test data suggest that the Code fatigue curves may not always be adequate in coolant environments. This paper reports the results of recent fatigue tests that examine the effects of steel type, strain rate, dissolved oxygen level, strain range, loading waveform, and surface morphology on the fatigue life of A 106-Gr B carbon steel and A533-Gr B low-alloy steel in water
A fracture mechanics approach for elastic-plastic materials has been used to evaluate the effects of...
Low cycle fatigue behaviors of SA508-3 low-alloy steel were investigated in room-temperature air, hi...
Recent test data indicate that the effects of the light water reactor (LWR) environment could signif...
The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant ...
The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant ...
The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant ...
Section 111 of the ASME Boiler and Pressure Vessel Code specifies fatigue design curves for structur...
The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant ...
This paper summarizes the work performed at Argonne National Laboratory on the fatigue of piping and...
The ASME Boiler and Pressure Vessel Code fatigue design curves for structural materials do not expli...
The existing fatigue strain vs. life (S-N) data, foreign and domestic, for carbon and low-alloy stee...
The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant ...
Section III of the ASME Boiler and Pressure Vessel Code specifies fatigue design curves for structur...
Fatigue tests have been conducted on Types 304 and 316NG stainless steels to evaluate the effects of...
The ASME Boiler and Pressure Vessel Code provides rules for the design of Class 1 components of nucl...
A fracture mechanics approach for elastic-plastic materials has been used to evaluate the effects of...
Low cycle fatigue behaviors of SA508-3 low-alloy steel were investigated in room-temperature air, hi...
Recent test data indicate that the effects of the light water reactor (LWR) environment could signif...
The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant ...
The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant ...
The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant ...
Section 111 of the ASME Boiler and Pressure Vessel Code specifies fatigue design curves for structur...
The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant ...
This paper summarizes the work performed at Argonne National Laboratory on the fatigue of piping and...
The ASME Boiler and Pressure Vessel Code fatigue design curves for structural materials do not expli...
The existing fatigue strain vs. life (S-N) data, foreign and domestic, for carbon and low-alloy stee...
The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant ...
Section III of the ASME Boiler and Pressure Vessel Code specifies fatigue design curves for structur...
Fatigue tests have been conducted on Types 304 and 316NG stainless steels to evaluate the effects of...
The ASME Boiler and Pressure Vessel Code provides rules for the design of Class 1 components of nucl...
A fracture mechanics approach for elastic-plastic materials has been used to evaluate the effects of...
Low cycle fatigue behaviors of SA508-3 low-alloy steel were investigated in room-temperature air, hi...
Recent test data indicate that the effects of the light water reactor (LWR) environment could signif...