Fatigue strain-life behavior of carbon and low-alloy steels, austenitic stainless steels, and Alloy 600 in LWR environments
Creators
- 1. Argonne National Lab., IL (United States)
Description
The existing fatigue strain vs. life (S-N) data, foreign and domestic, for carbon and low-alloy steels, austenitic stainless steels, and Alloy 600 used in the construction of nuclear power plant components have been compiled and categorized according to material, loading, and environmental conditions. Statistical models have been developed for estimating the effects of the various service conditions on the fatigue life of these materials. The results of a rigorous statistical analysis have been used to estimate the probability of initiating a fatigue crack. Data in the literature were reviewed to evaluate the effects of size, geometry, and surface finish of a component on its fatigue life. The fatigue S-N curves for components have been determined by adjusting the probability distribution curves for smooth test specimens for the effect of mean stress and applying design margins to account for the uncertainties due to component size/geometry and surface finish. The significance of the effect of environment on the current Code design curve and on the proposed interim design curves published in NUREG/CR-5999 is discussed. Estimations of the probability of fatigue cracking in sample components from BWRs and PWRs are presented
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as TI95016720; NTIS; GPO.Files
27004400.pdf
Files
(2.6 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 67 p.
- Report number
- NUREG/CR--6335
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27004400
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- BWR TYPE REACTORS; CARBON STEELS; COMPILED DATA; CRACK PROPAGATION; FATIGUE; INCONEL 600; LOW ALLOY STEELS; PWR TYPE REACTORS; REACTOR MATERIALS; SERVICE LIFE; STAINLESS STEELS; STANDARDS
- Descriptors DEC
- ALLOY-NI76CR15FE8; ALLOYS; ALUMINIUM ADDITIONS; CARBON ADDITIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; DATA; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; INCONEL ALLOYS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; LIFETIME; MATERIALS; MECHANICAL PROPERTIES; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIMONIC; NUMERICAL DATA; POWER REACTORS; REACTORS; STEELS; THERMAL REACTORS; TITANIUM ADDITIONS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract W-31109-ENG-38
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).
- Secondary number(s)
- ANL--95/15/.