| 摘要 |
A method for treating zirconium and zirconium alloys, in particular the zirconium alloys used in nuclear reactors which are water cooled, as a structural or casing material for fuels. The method consists in dissolving or maintaining a solid solution of the majority of carbon contained in these alloys by thermal or thermo-mechanical treatments carried out in the alpha + beta range or if necessary in the beta range followed by a rolling in alpha phase if necessary. The products obtained have a highly improved mechanical resistance under heat, in particular with regard to resistance to creep; they are particularly suitable for constructing casing tubes for fuels in water cooled nuclear reactors having a better resistance to distortion in relation to time. |
