Published February 1977
| Version v1
Report
Restricted
Creep-fatigue damage under multiaxial conditions
Description
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
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.
Files
Additional details
Additional titles
- Augmented title (English)
- LMFBR
Publishing Information
- Imprint Pagination
- 31 p.
- Report number
- SAND--76-0720
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8335303
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CREEP; FATIGUE; HIGH TEMPERATURE; LMFBR TYPE REACTORS; MATHEMATICAL MODELS; REACTOR COMPONENTS; REACTOR MATERIALS; SPECIFICATIONS; STRESSES
- Descriptors DEC
- BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; MECHANICAL PROPERTIES; REACTORS
Optional Information
- Secondary number(s)
- NUREG--0180.