Author: W. B. Rotsey
Publisher:
ISBN:
Category : Cold working
Languages : en
Pages : 16
Book Description
The strain-aging behavior of annealed Zircaloy-2 in vacuum was studied as a function of deformation temperature, integrated fast-neutron dose, and degree of cold work. Strain aging occurred in the temperature range 200 to 500 C. Transmission electron microscopy showed that in the temperature range 300 to 450 C, dislocations were arranged in a cell structure, and that at 500 C two-dimensional hexagonal dislocation nets were present. Between 200 and 400 C, the strain aging was found to be due to the presence of oxygen; however, the origin of the strain aging between 400 and 500 C was not identified.
The Effect of Neutron Irradiation and Cold Work on the Strain-Aging Behavior of Zircaloy-2
Author: W. B. Rotsey
Publisher:
ISBN:
Category : Cold working
Languages : en
Pages : 16
Book Description
The strain-aging behavior of annealed Zircaloy-2 in vacuum was studied as a function of deformation temperature, integrated fast-neutron dose, and degree of cold work. Strain aging occurred in the temperature range 200 to 500 C. Transmission electron microscopy showed that in the temperature range 300 to 450 C, dislocations were arranged in a cell structure, and that at 500 C two-dimensional hexagonal dislocation nets were present. Between 200 and 400 C, the strain aging was found to be due to the presence of oxygen; however, the origin of the strain aging between 400 and 500 C was not identified.
Publisher:
ISBN:
Category : Cold working
Languages : en
Pages : 16
Book Description
The strain-aging behavior of annealed Zircaloy-2 in vacuum was studied as a function of deformation temperature, integrated fast-neutron dose, and degree of cold work. Strain aging occurred in the temperature range 200 to 500 C. Transmission electron microscopy showed that in the temperature range 300 to 450 C, dislocations were arranged in a cell structure, and that at 500 C two-dimensional hexagonal dislocation nets were present. Between 200 and 400 C, the strain aging was found to be due to the presence of oxygen; however, the origin of the strain aging between 400 and 500 C was not identified.
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
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
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
NUREG/CR.
Author: U.S. Nuclear Regulatory Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 68
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 68
Book Description
Creep of Zirconium Alloys in Nuclear Reactors
Author:
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 308
Book Description
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 308
Book Description
Zirconium in the Nuclear Industry
Author: Craig M. Eucken
Publisher: ASTM International
ISBN: 080311463X
Category : Nuclear fuel claddings
Languages : en
Pages : 794
Book Description
The proceedings of the Ninth International Symposium on [title], held in Kobe, Japan, November 1990, address current trends in the development, performance, and fabrication of zirconium alloys for nuclear power reactors. the bulk of the most recent work on zirconium alloy behavior has concerned corr
Publisher: ASTM International
ISBN: 080311463X
Category : Nuclear fuel claddings
Languages : en
Pages : 794
Book Description
The proceedings of the Ninth International Symposium on [title], held in Kobe, Japan, November 1990, address current trends in the development, performance, and fabrication of zirconium alloys for nuclear power reactors. the bulk of the most recent work on zirconium alloy behavior has concerned corr
Creep of Zirconium Alloys in Nuclear Reactors
Author: D. G. Franklin
Publisher: ASTM International
ISBN: 9780803102590
Category : Science
Languages : en
Pages : 322
Book Description
Publisher: ASTM International
ISBN: 9780803102590
Category : Science
Languages : en
Pages : 322
Book Description
Reactor Technology
Author:
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 448
Book Description
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 448
Book Description