Zirconium alloys
AssigneeCommissariat a l'Energie Atomique
InventorsJean-Mathieu Frenkel, Jacques Pelchat, Michel Weisz
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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.
Claims4
In a method of manufacturing fuel cans and pressure tubes from Zircaloy-2 or Zircaloy-4 for use in nuclear reactors the improvement wherein said fuel cans or pressure tubes are annealed at a temperature from 400.degree.C to 750.degree.C for a sufficient period of time to cause recrystallization, said period being at least 1/2 hour.
Dependencies are inferred from the claim text.