Creep-fatigue damage under multiaxial conditions. [LMFBR]
Technical Report
·
OSTI ID:7216055
ASME Code rules for design against creep-fatigue damage for Class 1 nuclear components operating at elevated temperatures are currently being studied by ASME working groups and task forces with a view toward major modification. In addition, the design rules being developed for Class 2 and Class 3 components would be affected by any major modifications of Class 1 Rules. The report represents an attempt to evaluate the differences between two competing procedures--linear damage summation and strainrange partitioning--for multiaxial stress conditions. A modified version of strainrange partitioning is also developed to alleviate some limitations on nonproportional loading.
- Research Organization:
- Sandia Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- EY-76-C-04-0789
- OSTI ID:
- 7216055
- Report Number(s):
- SAND-76-0720; NUREG-0180
- Country of Publication:
- United States
- Language:
- English
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210500* -- Power Reactors
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HIGH TEMPERATURE
LIQUID METAL COOLED REACTORS
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