A study on the effect of Cu on the corrosion characteristics of Zr Alloys
- 1. Hanyang Univ., Seoul (Korea, Republic of)
Description
Zr-Cu binary alloys for nuclear fuel cladding were prepared by changing Cu content from 0.1wt.% to 0.8wt.% to investigate the effect of Cu on the corrosion behavior in water at 360 .deg. C under a pressure of 2660 psi. Specimens containing 0.1∼0.5wt.%Cu had the black and uniform oxide film and the transition of corrosion rate didn't occur during 50 day corrosion test. However, 0.8wt.%Cu specimen had the white oxide film and the transition of corrosion rate occurred at the 10 day corrosion test. The weight gain in pre-transition regime generally decreased with the decreasing Cu content from 0.8 to 0.2wt.% though 0.1wt.%Cu specimen showed higher weight gain than 0.2wt.%Cu specimen. Cu content had no effect on changing the oxide structure formed in pre-transition regime but decreased electrical resistivity of the oxide due to short-circuit effect of precipitate. The fraction of precipitates in the Zr-Cu binary alloys, identified as tetragonal Zr2Cu, increased with increasing Cu content. Increase in the fraction of precipitates is though to be responsible for the increase in weight gain
Additional details
Publishing Information
- Journal Title
- Journal of the Korean Institute of Metals and Materials
- Journal Volume
- 36
- Journal Issue
- 9
- Series
- 18 refs, 8 figs, 2 tabs
- Journal Page Range
- p. 1490-1496
- ISSN
- 0253-3847
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 36036323
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CLADDING; COPPER; CORROSION; HEAT TREATMENTS; NUCLEAR FUELS; OXIDES; PRECIPITATION; PRESSURE VESSELS; ZIRCONIUM
- Descriptors DEC
- CHALCOGENIDES; CHEMICAL REACTIONS; CONTAINERS; DEPOSITION; ELEMENTS; ENERGY SOURCES; FUELS; MATERIALS; METALS; OXYGEN COMPOUNDS; REACTOR MATERIALS; SEPARATION PROCESSES; SURFACE COATING; TRANSITION ELEMENTS