SciTech Connect

Title: Statistical analysis of fatigue strain-life data for carbon and low-alloy steels

Statistical analysis of fatigue strain-life data for carbon and low-alloy steels The existing fatigue strain vs life (S-N) data, foreign and domestic, for carbon and low-alloy steels used in the construction of nuclear power plant components have been compiled and categorized according to material, loading, and environmental conditions. A statistical model has been developed for estimating the effects of the various test conditions on fatigue life. 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 applying design margins for size, geometry, and surface finish to crack initiation curves estimated from the model.
Authors: ;
Publication Date:
OSTI Identifier:105096
Report Number(s):ANL/ET/CP--83023; CONF-950740--85
ON: TI95014083; TRN: 95:020272
DOE Contract Number:W-31-109-ENG-38
Resource Type:Conference
Data Type:
Resource Relation:Conference: Joint American Society of Mechanical Engineers (ASME)/Japan Society of Mechanical Engineers (JSME) pressure vessels and piping conference, Honolulu, HI (United States), 23-27 Jul 1995; Other Information: PBD: Mar 1995
Research Org:Argonne National Lab., IL (United States)
Sponsoring Org:Nuclear Regulatory Commission, Washington, DC (United States)
Country of Publication:United States
Language:English
Subject: 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 36 MATERIALS SCIENCE; 99 MATHEMATICS, COMPUTERS, INFORMATION SCIENCE, MANAGEMENT, LAW, MISCELLANEOUS; CARBON STEELS; FATIGUE; STRAINS; STATISTICAL MODELS; LOW ALLOY STEELS; BWR TYPE REACTORS; PWR TYPE REACTORS; MECHANICAL PROPERTIES