Measuring and testing – Specimen stress or strain – or testing by stress or strain... – By loading of specimen
Reexamination Certificate
2005-06-21
2005-06-21
Lefkowitz, Edward (Department: 2855)
Measuring and testing
Specimen stress or strain, or testing by stress or strain...
By loading of specimen
C073S788000
Reexamination Certificate
active
06907791
ABSTRACT:
A method for calculating a fatigue usage factor of a component in a nuclear reactor includes determining a flow scaling factor for each stress component of a stress cycle, applying the flow scaling factor to rapid cycling stress conditions, and performing a fatique evaluation by calculating a fatigue usage factor using the flow scaling factor. The flow scaling factor is a ratio of a temperature fluctuation ratio at a first reactor operating condition divided by a temperature fluctuation ratio at a second reactor operating condition. The temperature fluctuation ratio is defined as a ratio of the metal temperature range over the fluid temperature range.
REFERENCES:
ASME Boiler and Pressure Vessel Code, The American Society of Mechanical Engineers, 1989, pp. 77, 79, 80, 81, FIG. I-9.2.1 and FIG. I-9.1.
Branlund Betty Jane
Choe Hwang
Sridhar Bettadapur Narayanarao
Armstrong Teasdale LLP
General Electric Company
Lefkowitz Edward
Martir Lilybett
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