The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant components. The Code specifies fatigue design curves for structural materials. However, the effects of light water reactor (LWR) coolant environments are not explicitly addressed by the Code design curves. Existing fatigue strain-vs.-life ({var_epsilon}-N) data illustrate potentially significant effects of LWR coolant environments on the fatigue resistance of pressure vessel and piping steels. This report provides an overview of the existing fatigue {var_epsilon}-N data for carbon and low-alloy steels and wrought and cast austenitic SSs to define the effects of key material, loading, and environmental parameters on the fatigue lives of the st...
The existing fatigue strain versus life (S-N) data for materials used in nuclear power plant compon...
The existing fatigue strain versus life (S-N) data for materials used in nuclear power plant compon...
The existing fatigue strain versus life (S-N) data for materials used in nuclear power plant compon...
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 ...
This paper summarizes the work performed at Argonne National Laboratory on the fatigue of piping and...
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 ...
SME Boiler and Pressure Vessel Code provides construction of nuclear power plant components. Figure ...
The ASME Boiler and Pressure Vessel Code provides rules for the design of Class 1 components of nucl...
Section 111 of the ASME Boiler and Pressure Vessel Code specifies fatigue design curves for structur...
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 existing fatigue strain versus life (S-N) data for materials used in nuclear power plant compone...
The existing fatigue strain versus life (S-N) data for materials used in nuclear power plant compon...
The existing fatigue strain versus life (S-N) data for materials used in nuclear power plant compon...
The existing fatigue strain versus life (S-N) data for materials used in nuclear power plant compon...
The existing fatigue strain versus life (S-N) data for materials used in nuclear power plant compon...
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 ...
This paper summarizes the work performed at Argonne National Laboratory on the fatigue of piping and...
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 ...
SME Boiler and Pressure Vessel Code provides construction of nuclear power plant components. Figure ...
The ASME Boiler and Pressure Vessel Code provides rules for the design of Class 1 components of nucl...
Section 111 of the ASME Boiler and Pressure Vessel Code specifies fatigue design curves for structur...
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 existing fatigue strain versus life (S-N) data for materials used in nuclear power plant compone...
The existing fatigue strain versus life (S-N) data for materials used in nuclear power plant compon...
The existing fatigue strain versus life (S-N) data for materials used in nuclear power plant compon...
The existing fatigue strain versus life (S-N) data for materials used in nuclear power plant compon...
The existing fatigue strain versus life (S-N) data for materials used in nuclear power plant compon...