Corrosion and wear resistant coating on zirconium alloy cladding
US10350856B2 · kind B2 · utility
0Cited by
6References
10Claims
0Family size
Assignee
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Key dates
| Filing date | Nov 2, 2017 |
| Grant date | Jul 16, 2019 |
| Priority date | — |
| Expiry date | Nov 2, 2037 |
Classification
- Technology area (CPC Y)Emerging Cross-Sectional Technologies
- CPC primaryY02E30/30
- WIPO fieldEngines, pumps, turbines
- WIPO sectorMechanical engineering
Abstract
The invention relates to compositions and methods for coating a zirconium alloy cladding of a fuel element for a nuclear water reactor. The composition includes a master alloy including one or more alloying elements selected from chromium, silicon and aluminum, a chemical activator and an inert filler. The alloying element(s) is deposited or are co-deposited on the cladding using a pack cementation process. When the coated zirconium alloy cladding is exposed to and contacted with water in a nuclear reactor, a protective oxide layer can form on the coated surface of the cladding.
Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.