Published October 2017
| Version v1
Journal article
Study on high-cycle fatigue behavior for TA16 and 690 tube
Creators
- 1. Science and Technology on Reactor Fuel and Material Laboratory, Nuclear Power Institute of China, Chengdu (China)
Description
The high-cycle fatigue experiments for steam generator tube including TA16 and 690 were conducted under axial loadings. The environments were at room temperature in air. The S-N curves were processed according to the experimental data, and the fatigue limit of the cycle is obtained by fitting formula. The fracture morphology was observed by SEM, and the fracture morphology presents areas of crack initiation, crack growth and fracture. (authors)
Additional details
Publishing Information
- Journal Title
- Nuclear Power Engineering
- Journal Volume
- 38
- Journal Issue
- 5
- Journal Page Range
- p. 129-131
- ISSN
- 0258-0926
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 52062152
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- CRACK PROPAGATION; DIAGRAMS; EXPERIMENTAL DATA; FATIGUE; FRACTURES; MORPHOLOGY; REACTOR MATERIALS; SCANNING ELECTRON MICROSCOPY; STEAM GENERATORS; TEMPERATURE RANGE 0273-0400 K; TUBES
- Descriptors DEC
- BOILERS; DATA; ELECTRON MICROSCOPY; FAILURES; INFORMATION; MATERIALS; MECHANICAL PROPERTIES; MICROSCOPY; NUMERICAL DATA; TEMPERATURE RANGE; VAPOR GENERATORS
Optional Information
- Notes
- 2 figs., 7 tabs.