Recent test data indicate that the effects of the light water reactor (LWR) environment could significantly reduce the fatigue resistance of materials used in the reactor coolant pressure boundary components of operating nuclear power plants. Argonne National Laboratory has developed interim fatigue curves based on test data simulating LWR conditions, and published them in NUREG/CR-5999. In order to assess the significance of these interim fatigue curves, fatigue evaluations of a sample of the components in the reactor coolant pressure boundary of LWRs were performed. The sample consists of components from facilities designed by each of the four US nuclear steam supply system vendors. For each facility, six locations were studied including ...
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...
Fatigue and environmentally assisted cracking of piping, pressure vessel cladding, and core componen...
Recent test data indicate that the effects of the light water reactor (LWR) environment could signif...
This paper summarizes the work performed at Argonne National Laboratory on the fatigue of piping and...
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 ...
ABSTRACT A number of technical challenges have been identified in applying current methods to evalua...
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 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 design of Class 1 components of nucl...
As part of the process of renewing the operating license for an additional 20 years after the origin...
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 fatigue design curves for structural materials do not expli...
Fatigue and environmentally assisted cracking of piping, pressure vessel cladding, and core componen...
Recent test data indicate that the effects of the light water reactor (LWR) environment could signif...
This paper summarizes the work performed at Argonne National Laboratory on the fatigue of piping and...
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 ...
ABSTRACT A number of technical challenges have been identified in applying current methods to evalua...
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 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 design of Class 1 components of nucl...
As part of the process of renewing the operating license for an additional 20 years after the origin...
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 fatigue design curves for structural materials do not expli...
Fatigue and environmentally assisted cracking of piping, pressure vessel cladding, and core componen...