Zirconium alloys

Details Zirconium alloys Zirconium alloys

1974-02-28

1976-06-15

Lovell, C.

Metal treatment

Process of modifying or maintaining internal physical...

Chemical-heat removing or burning of metal

148 115F, 176 88, 176 91R, C21D 126

Patent

active

039635341

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.

REFERENCES:
patent: 3148055 (1964-09-01), Kass et al.
patent: 3271205 (1966-09-01), Winton et al.
patent: 3567522 (1971-03-01), Thomas et al.
Zirconium, Miller, 2nd Ed. 1957 Academic Press N.Y.
AECD-3680, "Tensile Properties of Zr Alloys," Simcoe et al., Nov. 20, 1951, p. 29.

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