Patent · US Expired

Zirconium alloys

US3963534A · kind A · utility

19Cited by
3References
4Claims
0Family size

Assignee

Inventors

Key dates

Filing dateFeb 28, 1974
Grant dateJun 15, 1976
Priority date
Expiry dateFeb 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.