Nuclear fuel rod and method of manufacturing the cladding of such a rod
US5373541A · kind A · utility
Assignees
Inventors
Key dates
| Filing date | Jan 19, 1993 |
| Grant date | Dec 13, 1994 |
| Priority date | — |
| Expiry date | Jan 19, 2013 |
Classification
- Technology area (CPC Y)Emerging Cross-Sectional Technologies
- CPC primaryY02E30/30
- WIPO fieldMaterials, metallurgy
- WIPO sectorChemistry
Abstract
A nuclear fuel rod cladding for a water moderated and nuclear reactor comprises an inner portion of Zircaloy 4 and an outer portion of a zirconium-based alloy which contains by weight, besides zirconium and unavoidable impurities: PA1 0.35% to 0.65% tin PA1 0.18% to 0.25% iron PA1 0.07% to 0.13% chromium, and PA1 0.19% to 0.23% oxygen, with the sum of the iron, chromium, tin, and oxygen contents being less than 1.26% by weight. It may alternatively or additionally comprise 0.80% to 1.20% by weight niobium and then the oxygen content is in the range 0.10% to 0.16% by weight. The thickness of the outer layer is 10% to 25% of the total thickness of the cladding. In a modification, up to 0.5% of iron, chromium, niobium is replaced by an equivalent content of vanadium.
Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.