Published August 2014
| Version v1
Journal article
Measurement of fatigue crack growth rate of reactor structural material in air based on DCPD method
- 1. Corrosion Laboratory for Nuclear Power Materials of Shanghai Jiaotong University, Shanghai (China)
- 2. Shanghai Key Laboratory for Nuclear Power Engineering, Shanghai (China)
Description
The principles and details of direct current potential drop (DCPD) in monitoring the crack growth of reactor structural materials was introduced in this paper. Based on this method, the fatigue crack growth rate (CGR) of typical structural materials in nuclear power systems was measured. The effects of applied load, load ratio and loading frequency on the fatigue crack growth rate of reactor structural materials were discussed. The result shows that the fatigue crack growth rate of reactor structural materials depends on the hardness of materials, and the harder the material is, the higher the rate of crack growth is. (authors)
Additional details
Identifiers
Publishing Information
- Journal Title
- Atomic Energy Science and Technology
- Journal Volume
- 48
- Journal Issue
- 8
- Journal Page Range
- p. 1386-1391
- ISSN
- 1000-6931
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 48088584
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- AIR; CRACK PROPAGATION; DIRECT CURRENT; DYNAMIC LOADS; ELECTRIC POTENTIAL; FATIGUE; HARDNESS; MATERIALS; MONITORING; NUCLEAR POWER PLANTS; REACTORS
- Descriptors DEC
- CURRENTS; ELECTRIC CURRENTS; FLUIDS; GASES; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS
Optional Information
- Notes
- 8 figs., 3 tabs., 18 refs.; http://dx.doi.org/10.7538/yzk.2014.48.08.1386