Zirconium alloy for improving resistance to oxidation at very high temperature and fabrication method thereof
US9421740B2 · kind B2 · utility
Assignees
Inventors
Key dates
| Filing date | Nov 7, 2012 |
| Grant date | Aug 23, 2016 |
| Priority date | — |
| Expiry date | Apr 30, 2033 |
Classification
- Technology area (CPC Y)Emerging Cross-Sectional Technologies
- CPC primaryY10T428/12812
- WIPO fieldSurface technology, coating
- WIPO sectorChemistry
Abstract
A zirconium alloy for use in nuclear fuel assemblies is provided, which provides increased resistance against oxidation and corrosion and also improved bonding with parent material, because pure metallic material such as silicon (Si) or chromium (Cr) is evenly coated on the surface of the parent material by plasma spraying. Because the plasma spray coating used to coat the pure metallic material on the zirconium alloy does not require vacuum equipment and also is not limited due to the shape of the coated product, this is particularly useful when evenly treating the surface of the component such as 4 m-long tube or spacer grip arrangement which is very complicated in shape. Furthermore, because the coated zirconium alloy confers excellent resistance to oxidation and corrosion under emergency such as accident as well as normal service condition, both the economic and safety aspects of nuclear fuel are improved.
Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.