Author: D. Lee
Publisher:
ISBN:
Category : Fractures (materials)
Languages : en
Pages : 15
Book Description
The roles of stress state and crystallographic texture on plastic flow fracture and fracture behavior were examined for Zircaloy-2 sheet specimens irradiated to fluences of 0.7 to 1.9 x 1021 neutrons/cm2 (E > 1 MeV) at 327°C. The extent of strengthening achieved by texture was determined by comparing the level of flow strength obtained under the plane strain loading condition to that of simple uniaxial tension, all at the test temperature of 250°C. It was demonstrated that the relative aspects of texture strengthening were retained in the post-irradiation tests; that is, the material with the peak basal pole density parallel to the sheet normal evidenced less ductility than that with the peak basal pole density inclined at 30 deg to the sheet normal. Supporting evidence is presented in terms of the changes in flow stress and ductility with texture and by the magnitude of R, the ratio of the transverse plastic strains. Plane strain loading increased the flow stress by 66 percent in the material having the peak basal pole density parallel to the sheet normal, but did not change the flow stress for material with the peak pole density inclined > 60 deg to the sheet normal. Texture strengthening persisted to the maximum fluence tested, suggesting a strong texture effect on the mechanical behavior of irradiated materials. The overall level of strain at fracture was substantially reduced by irradiation. The deformation and fracture modes were also strongly affected by texture as well as by the loading methods. The irradiated Zircaloy sheet with the peak basal pole density in the normal direction tended to deform by means of sharply defined deformation bands; intersection of these bands also leads to initiation of fracture. In the other materials (peak basal pole densities inclined to the normal by angles > 30 deg) the deformation bands tended to be more diffuse.
Strength and Ductility of Neutron Irradiated and Textured Zircaloy-2
Author: D. Lee
Publisher:
ISBN:
Category : Fractures (materials)
Languages : en
Pages : 15
Book Description
The roles of stress state and crystallographic texture on plastic flow fracture and fracture behavior were examined for Zircaloy-2 sheet specimens irradiated to fluences of 0.7 to 1.9 x 1021 neutrons/cm2 (E > 1 MeV) at 327°C. The extent of strengthening achieved by texture was determined by comparing the level of flow strength obtained under the plane strain loading condition to that of simple uniaxial tension, all at the test temperature of 250°C. It was demonstrated that the relative aspects of texture strengthening were retained in the post-irradiation tests; that is, the material with the peak basal pole density parallel to the sheet normal evidenced less ductility than that with the peak basal pole density inclined at 30 deg to the sheet normal. Supporting evidence is presented in terms of the changes in flow stress and ductility with texture and by the magnitude of R, the ratio of the transverse plastic strains. Plane strain loading increased the flow stress by 66 percent in the material having the peak basal pole density parallel to the sheet normal, but did not change the flow stress for material with the peak pole density inclined > 60 deg to the sheet normal. Texture strengthening persisted to the maximum fluence tested, suggesting a strong texture effect on the mechanical behavior of irradiated materials. The overall level of strain at fracture was substantially reduced by irradiation. The deformation and fracture modes were also strongly affected by texture as well as by the loading methods. The irradiated Zircaloy sheet with the peak basal pole density in the normal direction tended to deform by means of sharply defined deformation bands; intersection of these bands also leads to initiation of fracture. In the other materials (peak basal pole densities inclined to the normal by angles > 30 deg) the deformation bands tended to be more diffuse.
Publisher:
ISBN:
Category : Fractures (materials)
Languages : en
Pages : 15
Book Description
The roles of stress state and crystallographic texture on plastic flow fracture and fracture behavior were examined for Zircaloy-2 sheet specimens irradiated to fluences of 0.7 to 1.9 x 1021 neutrons/cm2 (E > 1 MeV) at 327°C. The extent of strengthening achieved by texture was determined by comparing the level of flow strength obtained under the plane strain loading condition to that of simple uniaxial tension, all at the test temperature of 250°C. It was demonstrated that the relative aspects of texture strengthening were retained in the post-irradiation tests; that is, the material with the peak basal pole density parallel to the sheet normal evidenced less ductility than that with the peak basal pole density inclined at 30 deg to the sheet normal. Supporting evidence is presented in terms of the changes in flow stress and ductility with texture and by the magnitude of R, the ratio of the transverse plastic strains. Plane strain loading increased the flow stress by 66 percent in the material having the peak basal pole density parallel to the sheet normal, but did not change the flow stress for material with the peak pole density inclined > 60 deg to the sheet normal. Texture strengthening persisted to the maximum fluence tested, suggesting a strong texture effect on the mechanical behavior of irradiated materials. The overall level of strain at fracture was substantially reduced by irradiation. The deformation and fracture modes were also strongly affected by texture as well as by the loading methods. The irradiated Zircaloy sheet with the peak basal pole density in the normal direction tended to deform by means of sharply defined deformation bands; intersection of these bands also leads to initiation of fracture. In the other materials (peak basal pole densities inclined to the normal by angles > 30 deg) the deformation bands tended to be more diffuse.
Zirconium in Nuclear Applications
Author: Schemel JH.
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 532
Book Description
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 532
Book Description
Effects of Cold Work and Neutron Irradiation on the Tensile Properties of Zircaloy-2
Author: Arden Lee Bement (Jr.)
Publisher:
ISBN:
Category : Metallurgy
Languages : en
Pages : 214
Book Description
Publisher:
ISBN:
Category : Metallurgy
Languages : en
Pages : 214
Book Description
Effects of Cold Work and Neutron Irradiation on the Tensile Properties of Zircaloy-2
Author: A. L. Bement
Publisher:
ISBN:
Category : Zirconium-tin alloys
Languages : en
Pages : 416
Book Description
Publisher:
ISBN:
Category : Zirconium-tin alloys
Languages : en
Pages : 416
Book Description
Zirconium in Nuclear Applications
Author: J. H. Schemel
Publisher: ASTM International
ISBN: 9780803107571
Category : Science
Languages : en
Pages : 544
Book Description
Publisher: ASTM International
ISBN: 9780803107571
Category : Science
Languages : en
Pages : 544
Book Description
Nuclear Science Abstracts
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 850
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 850
Book Description
Effects of Neutron Irradiation on the Flow and Fracture Behavior of Zircaloy-2
Author: A. L. Bement
Publisher:
ISBN:
Category : Metallurgy
Languages : en
Pages : 44
Book Description
Publisher:
ISBN:
Category : Metallurgy
Languages : en
Pages : 44
Book Description
Zirconium in the Nuclear Industry
Author: Leo F. P. Van Swam
Publisher: ASTM International
ISBN: 0803111991
Category : Nuclear fuel claddings
Languages : en
Pages : 781
Book Description
Publisher: ASTM International
ISBN: 0803111991
Category : Nuclear fuel claddings
Languages : en
Pages : 781
Book Description
Neutron Irradiation Effects on the Tensile Properties of Zircaloy-2
Author: R. S. Kemper
Publisher:
ISBN:
Category : Neutron irradiation
Languages : en
Pages : 52
Book Description
Publisher:
ISBN:
Category : Neutron irradiation
Languages : en
Pages : 52
Book Description
Evaluating Strength and Ductility of Irradiated Zircaloy, Task 5
Author:
Publisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 40
Book Description
Publisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 40
Book Description