Zirconium alloys
US3963534A · kind A · utility
19Cited by
3References
4Claims
0Family size
Assignee
Inventors
Key dates
| Filing date | Feb 28, 1974 |
| Grant date | Jun 15, 1976 |
| Priority date | — |
| Expiry date | Feb 28, 1994 |
Classification
- Technology area (CPC Y)Emerging Cross-Sectional Technologies
- CPC primaryY10S376/90
- WIPO fieldMaterials, metallurgy
- WIPO sectorChemistry
Abstract
In a method of fabrication of nuclear reactor components such as fuel cans and pressure tubes, use is made of zirconium alloys such as Zircaloy 2 or Zircaloy 4 having an oxygen content of 0.14 to 0.25 % by weight. The components are subjected to an annealing operation at a temperature within the range of 400.degree. to 750.degree.C and especially 525.degree. to 750.degree.C over a period of approximately two hours, thus resulting in recrystallization.
Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.