Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 62
Book Description
Deformation Creep and Fracture in Alpha Zirconium Alloys
Deformation and Fracture of Alpha Zirconium Alloys
DEFORMATION AND FRACTURE OF ALPHA ZIRCONIUM ALLOYS (THE DUCTILITY OF ZIRCONIUM AND ITS ALLOYS). Final Report
Applications-Related Phenomena in Zirconium and Its Alloys
Author: Committee B-10 Staff
Publisher: ASTM International
ISBN:
Category : Uranium
Languages : en
Pages : 393
Book Description
Publisher: ASTM International
ISBN:
Category : Uranium
Languages : en
Pages : 393
Book Description
Creep of Zirconium Alloys in Nuclear Reactors
Creep and Creep Fracture of Zirconium and Zirconium Alloys
Interim Report of Creep Behavior of Zircaloy-2 and -3
Author: W. D. McMullen
Publisher:
ISBN:
Category : Zirconium alloys
Languages : en
Pages : 28
Book Description
Publisher:
ISBN:
Category : Zirconium alloys
Languages : en
Pages : 28
Book Description
Localization of Deformation and Fracture of Zirconium Alloys
Deformation of Irradiated Zirconium-Niobium Alloys
Author: CE. Ells
Publisher:
ISBN:
Category : Fracture (materials)
Languages : en
Pages : 17
Book Description
This review summarizes the flow and fracture behavior of irradiated zirconium-niobium alloys. It is confined to the alloys currently used in power reactors, namely Zr-1.ONb, Zr-2.5Nb, and Zr-2.5Nb-0.5Cu, and of these, most of the literature deals with the Zr-2.5Nb alloy. Both before and after irradiation, the Zr-2.5Nb alloy has a good combination of strength and ductility; these properties have enabled reactor designers to replace Zircaloy with Zr-2.5Nb in applications where the superior in-reactor creep resistance of the latter alloy is important. The good ductility of the irradiated Zr-2.5Nb alloy, however, is dependent on the alloy remaining below the beta transus in the final stages of heat-treatment/fabrication before irradiation. Although there is much information on the deformation of the irradiated material relevant to reactor design, the basic understanding of the deformation is in an early stage of development.
Publisher:
ISBN:
Category : Fracture (materials)
Languages : en
Pages : 17
Book Description
This review summarizes the flow and fracture behavior of irradiated zirconium-niobium alloys. It is confined to the alloys currently used in power reactors, namely Zr-1.ONb, Zr-2.5Nb, and Zr-2.5Nb-0.5Cu, and of these, most of the literature deals with the Zr-2.5Nb alloy. Both before and after irradiation, the Zr-2.5Nb alloy has a good combination of strength and ductility; these properties have enabled reactor designers to replace Zircaloy with Zr-2.5Nb in applications where the superior in-reactor creep resistance of the latter alloy is important. The good ductility of the irradiated Zr-2.5Nb alloy, however, is dependent on the alloy remaining below the beta transus in the final stages of heat-treatment/fabrication before irradiation. Although there is much information on the deformation of the irradiated material relevant to reactor design, the basic understanding of the deformation is in an early stage of development.