Damage assessment of low-cycle fatigue by crack growth prediction. Development of growth prediction model and its application
Creators
- 1. Inst. of Nuclear Safety System, Inc., Mihama, Fukui (Japan)
Description
In this study, the fatigue damage was assumed to be equivalent to the crack initiation and its growth, and fatigue life was assessed by predicting the crack growth. First, a low-cycle fatigue test was conducted in air at room temperature under constant cyclic strain range of 1.2%. The crack initiation and change in crack size during the test were examined by replica investigation. It was found that a crack of 41.2 μm length was initiated almost at the beginning of the test. The identified crack growth rate was shown to correlate well with the strain intensity factor, whose physical meaning was discussed in this study. The fatigue life prediction model (equation) under constant strain range was derived by integrating the crack growth equation defined using the strain intensity factor, and the predicted fatigue lives were almost identical to those obtained by low-cycle fatigue tests. The change in crack depth predicted by the equation also agreed well with the experimental results. Based on the crack growth prediction model, it was shown that the crack size would be less than 0.1 mm even when the estimated fatigue damage exceeded the critical value of the design fatigue curve, in which a twenty-fold safety margin was used for the assessment. It was revealed that the effect of component size and surface roughness, which have been investigated empirically by fatigue tests, could be reasonably explained by considering the crack initiation and growth. Furthermore, the environmental effect on the fatigue life was shown to be brought about by the acceleration of crack growth. (author)
Additional details
Publishing Information
- Journal Title
- Nippon Kikai Gakkai Ronbunshu, A Hen
- Journal Volume
- 78
- Journal Issue
- 795
- Journal Page Range
- p. 1518-1533
- ISSN
- 0387-5008
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 45080429
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CRACK PROPAGATION; CRACKS; DAMAGE; FATIGUE; FORECASTING; LIFETIME; MATHEMATICAL MODELS; MECHANICAL TESTS; NUCLEAR POWER PLANTS; PIPES; PRESSURE VESSELS; STAINLESS STEELS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CONTAINERS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS TESTING; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; POWER PLANTS; STEELS; TESTING; THERMAL POWER PLANTS; TRANSITION ELEMENT ALLOYS; TUBES
Optional Information
- Notes
- 65 refs., 15 figs., 2 tabs.